ML19219A058
| ML19219A058 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 08/07/2019 |
| From: | NRC/OGC |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| 52-047-ESP, ASLBP 17-954-01-ESP-BD02, RAS 55139 | |
| Download: ML19219A058 (357) | |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of TENNESSEE VALLEY AUTHORITY Docket No. 52-047-ESP (Clinch River Nuclear Site Early Site Permit Application)
Hearing Exhibit Exhibit Number: NRC-010 Exhibit
Title:
Clinch River Nuclear Site Early Site Permit Application, Rev. 1 -
Part 5, Emergency Planning (Dec. 15, 2017).
Clinch River Nuclear Site Early Site Permit Application Part 5A Emergency Plan (Site Boundary EPZ)
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Table of Contents 1.0 PURPOSE ....................................................................................................... 1 2.0 SCOPE ............................................................................................................ 3 2.1 APPENDICES ................................................................................................. 3 2.2 IMPLEMENTING PROCEDURES ................................................................... 3 2.3 STATE RADIOLOGICAL EMERGENCY PLAN ............................................. 4 2.4 NATIONAL RESPONSE FRAMEWORK ........................................................ 5 3.0 PROCESS ....................................................................................................... 6 3.1 ROLES AND RESPONSIBILITIES ................................................................. 6 3.1.1 Emergency Management Organization (Concept of Operations) ............. 6 3.2 ONSITE ORGANIZATION .............................................................................. 6 3.3 OFFSITE ORGANIZATION ............................................................................. 7 3.3.1 CECC Director................................................................................................ 7 3.3.2 Assistant CECC Director .............................................................................. 8 3.3.3 Emergency Preparedness Staff Representative ......................................... 8 3.3.4 State Communicator ..................................................................................... 8 3.3.5 TVA Operations Duty Specialist ................................................................... 9 3.3.6 Emergency Duty Officer ................................................................................ 9 3.3.7 TVA State Liaison .......................................................................................... 9 3.3.8 CECC Plant Assessment Manager ............................................................... 9 3.3.9 Plant Assessment Coordinator .................................................................. 10 3.3.10 CECC Plant Assessment Team .................................................................. 10 3.3.11 Resource Support Coordinator .................................................................. 10 3.3.12 Engineering Representative ....................................................................... 11 3.3.13 Public Information Manager ....................................................................... 11 3.3.14 JIC Liaison ................................................................................................... 11 3.3.15 Public Information Writer ............................................................................ 11 3.3.16 Radiological Assessment Manager ........................................................... 11 3.3.17 Radiological Assessment Coordinator ..................................................... 12 3.3.18 Environmental Assessor ............................................................................ 12 3.3.19 Dose Assessor............................................................................................. 13 3.3.20 Meteorologist ............................................................................................... 13 ii Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 3.3.21 Technical Advisors...................................................................................... 13 3.3.22 Boardwriter(s) .............................................................................................. 13 3.3.23 Management Services ................................................................................. 13 3.3.24 Local Support .............................................................................................. 13 3.3.25 Federal Agency Support ............................................................................. 14 3.3.26 Vendor Support ........................................................................................... 14 3.3.27 INPO .............................................................................................................. 14 4.0 EMERGENCY CONDITIONS ........................................................................ 16 4.1 CLASSIFICATION SYSTEM ......................................................................... 16 4.1.1 NOUE ............................................................................................................ 16 4.1.2 Alert .............................................................................................................. 17 4.1.3 Site Area Emergency................................................................................... 17 4.1.4 General Emergency ..................................................................................... 17 4.2 IDENTIFICATION OF EMERGENCY CLASSES .......................................... 18 5.0 EMERGENCY NOTIFICATION AND ACTIVATION OF PLAN .................... 19 5.1 ONSITE ......................................................................................................... 19 5.2 OFFSITE ....................................................................................................... 19 5.2.1 NOUE ............................................................................................................ 19 5.2.2 Alert .............................................................................................................. 20 5.2.3 Site Area Emergency................................................................................... 21 5.2.4 General Emergency ..................................................................................... 21 6.0 COMMUNICATIONS ..................................................................................... 23 6.1 EP TELEPHONE SYSTEM ........................................................................... 23 6.2 PLANT TELEPHONE SWITCHING EQUIPMENT ........................................ 23 6.3 PLANT OR BUILDING LOUDSPEAKER PAGING ...................................... 23 6.4 OFFSITE TELEPHONE COMMUNICATIONS .............................................. 23 6.5 EP NOTIFICATION SYSTEM ....................................................................... 24 6.6 TVA ENTERPRISE EMERGENCY NOTIFICATION SYSTEM ..................... 24 6.7 EP RADIO SYSTEM ..................................................................................... 24 6.8 OTHER RADIO COMMUNICATIONS ........................................................... 24 7.0 PUBLIC INFORMATION AND EDUCATION ................................................ 25 7.1 PURPOSE ..................................................................................................... 25 iii Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 7.2 RESPONSIBILITIES ..................................................................................... 25 7.2.1 CECC Director.............................................................................................. 25 7.2.2 JIC Spokesperson ....................................................................................... 25 7.2.3 Director, Public Relations & Corporate Information ................................ 25 7.2.4 Operations Communications ..................................................................... 25 7.3 PUBLIC INFORMATION FACILITIES .......................................................... 25 7.4 COORDINATION OF INFORMATION .......................................................... 26 7.5 PUBLIC EDUCATION ................................................................................... 26 7.6 EMPLOYEE COMMUNICATIONS ................................................................ 26 7.7 RUMOR CONTROL/PUBLIC INFORMATION ............................................. 26 7.8 TRAINING ..................................................................................................... 26 8.0 EMERGENCY RESPONSE FACILITIES, EQUIPMENT, AND SUPPLIES .. 27 8.1 NUCLEAR SITE FACILITIES ....................................................................... 27 8.1.1 Technical Support Center ........................................................................... 27 8.1.2 Operations Support Center ........................................................................ 27 8.1.3 Local Recovery Center ................................................................................ 27 8.1.4 Site Decontamination Facilities ................................................................. 28 8.1.5 Equipment, Supplies, and Supplemental Data ......................................... 28 8.2 CENTRAL EMERGENCY CONTROL CENTER ........................................... 28 8.3 RADIOLOGICAL MONITORING CONTROL CENTER ................................ 29 8.4 JOINT INFORMATION CENTER .................................................................. 29 9.0 ACCIDENT ASSESSMENT .......................................................................... 31 9.1 ONSITE ......................................................................................................... 31 9.2 OFFSITE ....................................................................................................... 31 9.2.1 General Information .................................................................................... 31 9.2.2 Sampling Team ............................................................................................ 33 9.2.3 Analyzing Environmental Samples ............................................................ 34 9.2.4 Meteorological Information ........................................................................ 34 9.2.5 Dose Assessment........................................................................................ 34 10.0 PROTECTIVE RESPONSE ........................................................................... 36 10.1 ONSITE PROTECTIVE ACTIONS FOR RADIOLOGICAL EVENTS ........... 36 10.2 ONSITE PROTECTIVE ACTIONS FOR HOSTILE ACTION EVENTS ......... 37 iv Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 10.3 OFFSITE ....................................................................................................... 37 11.0 RADIOLOGICAL PROTECTION .................................................................. 38 12.0 MEDICAL SUPPORT .................................................................................... 42 12.1 GENERAL INFORMATION ........................................................................... 42 12.1.1 Classification And Handling Of Medical Emergency Patients ................ 42 12.1.2 Noncontaminated-Nonirradiated ................................................................ 42 12.1.3 Irradiated-Noncontaminated ....................................................................... 42 12.1.4 Contaminated............................................................................................... 43 12.2 TRANSPORTATION OF INJURED PERSONNEL ....................................... 43 12.3 INTERAGENCY ASSISTANCE FROM REAC/TS ........................................ 43 13.0 TERMINATION AND RECOVERY ................................................................ 44 13.1 TERMINATION .............................................................................................. 44 13.2 RECOVERY ORGANIZATION ...................................................................... 46 13.2.1 Chief Nuclear Officer ................................................................................... 46 13.2.2 Senior Vice President Operations .............................................................. 46 13.2.3 Site Vice President ...................................................................................... 46 13.2.4 Vice President, Operations Support .......................................................... 46 13.2.5 CECC Public Information Manager ............................................................ 47 13.2.6 Vice President, Nuclear Licensing ............................................................. 47 13.2.7 Vice President, Engineering & Support ..................................................... 47 13.2.8 Vice President, Nuclear Oversight ............................................................. 47 13.2.9 Other TVA Resources ................................................................................. 47 13.3 ONSITE RECOVERY .................................................................................... 47 13.4 LOCAL RECOVERY CENTER ..................................................................... 48 13.5 OFFSITE RECOVERY .................................................................................. 48 14.0 DRILLS AND EXERCISES ........................................................................... 49 14.1 DRILLS.......................................................................................................... 49 14.1.1 Medical Emergency Drills ........................................................................... 49 14.1.2 Radiological Monitoring Drills .................................................................... 49 14.1.3 Rad Protection Drills ................................................................................... 49 14.1.4 Radiochemistry Drills .................................................................................. 49 14.1.5 Radiological Dose Assessment Drills ....................................................... 49 v Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 14.1.6 Fire Drills ...................................................................................................... 49 14.1.7 Communication Drills ................................................................................. 50 14.2 EXERCISES .................................................................................................. 50 14.3 SCENARIOS ................................................................................................. 50 14.4 CRITIQUES ................................................................................................... 51 15.0 TRAINING ..................................................................................................... 52 15.1 ONSITE ......................................................................................................... 52 15.2 OFFSITE ....................................................................................................... 52 15.3 PROFESSIONAL DEVELOPMENT TRAINING ........................................... 52 16.0 PLAN MAINTENANCE ................................................................................. 53 16.1 NP-REP ......................................................................................................... 53 16.2 EPIPs ............................................................................................................ 54 16.2.1 Document Identification .............................................................................. 54 16.2.2 Periodic Review ........................................................................................... 56 16.2.3 EPIP Changes .............................................................................................. 56 16.2.4 Distribution ........................................................ Error! Bookmark not defined.
16.3 DOCUMENT RELATIONSHIPS .................................................................... 58 16.4 AUDITS ......................................................................................................... 58 16.5 AGREEMENT LETTERS .............................................................................. 58 17.0 DEFINITIONS AND ACRONYMS ................................................................. 60 Justification for the Central Emergency Control Center....65 vi Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 1.0 PURPOSE The purpose of Part 5A is to provide sufficient information to ensure the compatibility of the proposed emergency plans (for onsite areas) with facility design features, site layout, and site location. In an effort to maintain consistency throughout the fleet, the content of Part 5A is based on the Tennessee Valley Authoritys (TVA) Nuclear Power Radiological Emergency Plan (NP-REP), Generic Part, which has been approved by the U.S. Nuclear Regulatory Commission (NRC) for use at all of the TVA operating nuclear facilities. Site-specific information is included in Appendix A to this Plan to address emergency planning for the Clinch River Nuclear (CRN) Site. This Plan addresses pertinent requirements and associated guidance contained in NUREG-0654, Revision 1, Supplement 2, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants - Criteria for Planning in an Early Site Permit Application (NUREG-0654 Supplement 2) to provide major features of the Emergency Plan. Information that was not available to TVA during the development of the CRN Site Early Site Permit Application (ESPA) will be addressed in the Combined License Application (COLA). Information to be addressed at COLA includes analysis normally found in a Design Certification Application and not currently available such as specific accident development details, staffing levels, required safety-related equipment.
In accordance with 10 CFR Part 52, Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants, Part 5A addresses the emergency planning requirements of Appendix E to 10 CFR Part 50, Section III, the Final Safety Analysis Report; Site Safety Analysis Report. Part 50 Appendix E states, The final safety analysis report or the site safety analysis report for an early site permit that includes major features of emergency plans under 10 CFR 52.17(b)(2)(i) of this chapter shall contain the plans for coping with emergencies. In addition, these regulations require that the application must contain the means which the standards of § 50.47(b) will be met.
In the development of this Plan, TVA has considered the applicable guidance provided in the following documents with consideration given to the proposed exemptions contained in Part 6 of the ESPA:
NUREG-0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (NUREG-0654).
NUREG-0654, Revision 1, Supplement 2.
Regulatory Guide 1.101, Revision 3, Emergency Planning and Preparedness for Nuclear Power Reactors (RG 1.101).
Section 13.3 of Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) (RG 1.70).
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Section 13.3 of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-0800).
As specified in NUREG-0654 and RG 1.101, this Plan provides for the following:
Adequate measures are taken to protect employees and the public that may be located within the Site Boundary.
Individuals having responsibilities during an emergency are properly trained.
Procedures exist to provide the capability to cope with a spectrum of emergencies ranging from those of little consequence to major core melt.
Equipment is available to detect, assess, and mitigate the consequences of such occurrences.
Emergency action levels and procedures are established to assist in making decisions.
This Plan has been developed to respond to potential radiological emergencies at the CRN Site as they may apply to small modular reactors (SMRs). As discussed in Site Safety Analysis Report (SSAR) Section 13.3 of this EPSA, the SMR technologies under consideration do not have postulated design basis accidents that would result in dose consequences that are large enough to require offsite emergency planning, the overall scope of this plan delineates the actions necessary to safeguard onsite personnel (within the site boundary) and minimize damage to property. As discussed in Part 3 of this ESPA, for postulated beyond design basis accidents, analysis has concluded that, because of the slow progression rate, sufficient time is available to initiate appropriate mitigating actions to protect the health and safety of the public beyond the Site Boundary.
The NRC requires a level of emergency preparedness commensurate with the potential consequences to public health, safety, common defense, and security at the CRN Site. This Plan considers the proposed exemptions contained in Part 6 of the ESPA. Implementation of this Plan is not dependent on the comprehensive emergency management plan (CEMP) nor would TVA impose a requirement on offsite agencies to implement this Plan.
As addressed in the Federal Emergency Management Agencys (FEMA) Comprehensive Preparedness Guide 101, Developing and Maintaining Emergency Operations Plans (CPG-101), if determined appropriate, government officials may utilize a CEMP approach to emergency planning to implement ad hoc protective actions to protect the public.
The CRN Site ESPA (Part 5A, Emergency Plan) consists of this Generic Part and a site specific Appendix A.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 2.0 SCOPE This Plan provides information regarding emergency preparedness and response planning for the CRN Site and addresses organizational responsibilities, capabilities, actions, and guidelines for TVA during a radiological emergency. It also describes the centralized emergency management concept which was approved by the NRC Commissioners via COMJA-80-37 (January 21, 1981). Additional guidance regarding the centralized emergency management concept can also be found in NRC SECY-96-170 (August 5, 1996) and NRC SECY-10-0078 (June 16, 2010).
2.1 APPENDICES Additional Radiological Emergency Plan information specific to the CRN Site is included as the CRN Site ESPA (Part 5A, Emergency Plan / Appendix A); referred to in the remainder of this document as Appendix A.
Appendix A details facility features, capabilities, equipment, and responsibilities. The Generic Part together with Appendix A, describes the methods TVA will use to:
- 1. Detect an emergency condition.
- 2. Evaluate the severity of the problems.
- 3. Notify federal, State, and local agencies of the condition.
- 4. Activate emergency organizations.
- 5. Evaluate the possible offsite consequences.
- 6. Mitigate the consequences of the emergency.
Since TVAs authority is limited to TVA-owned and controlled property, the State of Tennessee (State) and local agencies are responsible for ordering and implementing actions offsite to protect the health and safety of the public. If determined appropriate, government officials may utilize a CEMP approach to emergency planning to implement ad hoc protective actions to protect the public.
2.2 IMPLEMENTING PROCEDURES TVA develops specific procedures to ensure that the Plan is implemented as designed. These implementing procedures are designed to ensure that emergencies are properly evaluated, rapid notifications made, and assessment and onsite protective actions performed. These procedures are compiled in the Emergency Plan Implementing Procedures (EPIPs). Site specific procedures for abnormal and emergency operation and control exist but are not included in the EPIPs. These plant operating procedures are designed to ensure the implementation of the EPIPs.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 2.3 STATE RADIOLOGICAL EMERGENCY PLAN The State Radiological Emergency Plan is referenced in Appendix A, Attachment 1. This Plan provides for the coordinated response of the State and affected local governments and defines roles and responsibilities.
As addressed in the Federal Emergency Management Agencys (FEMA) Comprehensive Preparedness Guide 101, Developing and Maintaining Emergency Operations Plans (CPG-101), if determined appropriate, government officials may utilize a CEMP approach to emergency planning to implement ad hoc protective actions to protect the public.
The responsibilities of these major organizations are summarized in Table 2-1.
TABLE 2-1 PRINCIPAL ORGANIZATIONAL RESPONSIBILITIES Local State TVA Command and Control X X X Warning X X X Notification Communications X X X Public Information X X X Emergency Assessment -- X X Public Health and Sanitation X X --
Social Services X -- --
Fire and Rescue X -- X Traffic Control X -- --
Emergency Medical Services X X X Law Enforcement X X --
Transportation X -- --
Protective Response X X --
Radiological Exposure Control X X X 4 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 2.4 NATIONAL RESPONSE FRAMEWORK The National Response Framework (NRF) Nuclear/ Radiological Incident Annex provides for timely, coordinated response by federal agencies to a fixed nuclear power plant facility incident.
The NRF is activated by either the affected State notifying the Department of Homeland Security (DHS), or the utility notifying the NRC of a radiological emergency at a nuclear plant site. The NRF is not included as part of the TVA Radiological Emergency Plan. Should additional radiological monitoring support be required the appropriate State agency will make the request through DHS. The persons authorized to request this assistance, the specific resources expected, and resources available to support the federal response are provided in the respective State plans.
The NRF may be used by federal agencies in radiological emergencies. The NRF primarily concerns offsite federal response in support of State and local governments with jurisdiction for the emergency. The NRF provides the federal government's concept of operations for responding to radiological emergencies, outlines federal policies and planning assumptions, and specifies authorities and responsibilities of each federal agency that may have a significant role in such emergencies. The Central Emergency Control Center (CECC) Director is the TVA representative authorized to request federal assistance. Such a request from TVA will be made to the NRC.
TVA will utilize the CECC in Chattanooga, Tennessee as the Emergency Operations Facility (EOF) for the Clinch River Nuclear Site. The CECC serves as the EOF for the other TVA nuclear plants (Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN)).This multi-site EOF was previously approved for use by the NRC in COMJA-80-37. Attachment 1 of this Plan provides additional description of and justification for the location of the CECC.
Because of the close proximity of the U.S. Department of Energy (DOE) Oak Ridge Reservation to the CRN Site, DOE response, should assistance be requested, is expected within 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Additional information about the NRF and available support is provided in NRC RIS 2005-13, NRC Incident Response and the National Response Plan (RIS 2005-13), NUREG-0728, Emergency Preparedness and Incident Response Programs (NUREG-0728) or the FEMA website (www.fema.gov) as well as in the Agency Emergency Response Plan (TVA-SPP-35.01).
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 3.0 PROCESS 3.1 ROLES AND RESPONSIBILITIES The development, implementation, and maintenance of the NP-REP is the responsibility of the TVA Nuclear organization. The General Manager, Support Services has delegated the authority for overall program control of the NP-REP to the Director, Emergency Preparedness as described below. Appendix A provides detailed staffing and organizational roles and responsibilities for the CRN Site minimum required Onsite Emergency Management Organization positions.
3.1.1 Emergency Management Organization (Concept of Operations)
The CRN Site Emergency Management Organization is divided into two categories; the Onsite Organization and the Offsite Emergency Organization. A block diagram of the Onsite Organization is presented in Appendix A and the Offsite Emergency Organization is presented in Figure 3-1. All designated Emergency Management Organization personnel are required to participate in the Fitness for Duty Program.
The Onsite Organization is comprised of the Site Emergency Director (SED) and technical staff located in the Technical Support Center (TSC), a Control Room staff of Operations personnel, and additional support personnel located in the Operations Support Center (OSC). The Onsite Organization is responsible for the onsite response to an emergency condition. Onsite activities are directed by the SED to include such functions as Control Room operations, technical assessment, emergency mitigation analysis, onsite radiation surveys, and dose tracking for site personnel.
The Offsite Organization is designated as the CECC staff. The CECC staff is comprised of a CECC Director, a supporting group of technical assistants, and representatives of other TVA organizations. The CECC Director and supporting technical assistants report to the CECC during an emergency as required. Other TVA organizations will send representatives to the CECC as requested by the CECC Director.
The CECC is responsible for directing and coordinating the overall TVA response to an emergency condition. Functions such as offsite radiological monitoring and dose assessment, public information, State and local government coordination, and additional plant assessment are handled by the CECC relieving the Onsite Organization of the many peripheral duties necessary for the successful emergency response.
3.2 ONSITE ORGANIZATION Under normal conditions the Site Vice President is in charge of activities at the site and the Plant Manager is responsible for the safe efficient operation of the plant. The person primarily responsible for mitigation of an emergency is the SED. Upon declaration of an emergency the Shift Manager (SM) on duty initially fills the position of SED and directs emergency response from the Control Room. This position is transferred to the TSC when that facility is activated.
Once the TSC is activated, the SED and the TSC can provide technical support to the Control Room as part of their overall response to the emergency.
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The CRN Site is staffed on a continual 24-hour basis. The minimum staffing requirements for plant operations are established in the plant Technical Specifications. The staff responsibilities are as outlined in the SSAR, and are unchanged during an emergency. The on-shift composition listed in Appendix A may be less than the minimum requirements for a period of time in order to accommodate unexpected absences of personnel provided action is taken to restore the composition within established time requirements.
Under emergency conditions, the normal plant staff is supplemented as shown in Appendix A.
Appendix A also provides descriptions of the responsibilities of the personnel who augment the normal plant operating organization. Support personnel will be notified to report as required by the situation. Staffing time for the augmenting forces is indicated in Appendix A. This time could vary slightly, depending upon the time of day, weather conditions, immediate availability of personnel, and radiological conditions.
The Onsite Organization augments the shift operations crew. If members of the Onsite Organization are not present when an emergency occurs, the SM on-duty, or a designated Unit Supervisor when acting as the SM, is designated the SED and acts as such until relieved by the SED assigned to the TSC.
Upon detection of a known or suspected emergency, the SM on-duty refers to a CRN-EPIP to determine the classification of the emergency. After determining the classification of the incident, the SM assumes the responsibilities of SED and initiates the appropriate procedure referenced by the CRN-EPIP. Emergency communications / notifications with State, local and federal agencies, along with staffing instructions for the emergency response facilities are specified in CRN-EPIPs.
CRN-EPIPs designate personnel who staff the Emergency Notification System (ENS) and Health Physics Network (HPN) (NRC FTS 2000 System) Communication Systems. CRN-EPIPs also designate the interface with the NRC during TSC operation.
3.3 OFFSITE ORGANIZATION Figure 3-1 provides a diagram of the Offsite Organization, including those positions that must respond within a prescribed time of an Alert or higher (see Section 4.0, Emergency Conditions) emergency declaration at the CRN Site. The prescribed response times for the Offsite Organization will be addressed in the COLA.
Activation for the CECC is accomplished within a prescribed time following declaration of an Alert or higher (see Section 4.0, Emergency Conditions) emergency classification at the CRN Site, depending upon time of day, weather conditions, or immediate availability of personnel.
The prescribed activation time for the CECC for an event at the CRN Site will be addressed in the COLA.
3.3.1 CECC Director The CECC Director has overall responsibility and authority for ensuring adequate TVA response. The CECC Director:
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Directs and coordinates TVA emergency response.
Reviews and approves TVA press releases (excluding initial report of event).
Reviews adequacy of information to news media/public.
Acts as the primary point of contact for official TVA positions or recommendations.
Ensures that key individuals are notified of the condition and severity of the events.
Ensures information relative to the plant status, radiological impacts, and protective measures is available to emergency responders.
Ensures sufficient information relative to the plant status, radiological impacts, and protective measures is made available to government officials to enable them to implement ad hoc protective measures (in accordance with a CEMP) for the protection of the public should they be determined appropriate by offsite officials.
Ensures NRC, U.S. Department of Energy (DOE), INPO, insurance underwriters, and the appropriate federal, State, and local agencies have been notified.
Ensures points of contact for key types of information from the CECC are provided.
Ensures 24-hour/day operations are established if required.
3.3.2 Assistant CECC Director An optional position that may be filled at the CECC Director's discretion to assist in carrying out duties. This position will be filled by a person qualified as CECC Director.
3.3.3 Emergency Preparedness Staff Representative The Emergency Preparedness (EP) Staff Representative:
Advises the CECC Director regarding the NP-REP.
Confirms the CECC is set up and operating properly.
Assists the CECC Director in operating the CECC by evaluating, compiling, documenting, and posting data concerning the emergency situation.
3.3.4 State Communicator The State Communicator:
Acts as the TVA primary communicator to the State.
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Clarifies information discrepancies and ensures pertinent information related to plant status, onsite response, and TVA dose assessment is provided to the State.
Further assists in providing TVA resource assistance, provides the State with technical advice as necessary, and assists the State Liaison (a State government representative) in briefings and coordinating responses to State inquiries.
3.3.5 TVA Operations Duty Specialist The position of Operations Duty Specialist (ODS) is staffed seven days a week, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.
After being notified of an emergency from the CRN Site, the ODS is responsible for making initial notification to the TVA REP Emergency Management Organization.
3.3.6 Emergency Duty Officer The Emergency Duty Officer (EDO) is responsible for establishing initial operation of the CECC in the event the NP-REP is activated at the Alert or higher (see Section 4.0, Emergency Conditions) emergency classification. The EDO is responsible for ensuring that appropriate initial notifications of TVA and offsite emergency organizations have been made for each emergency classification.
3.3.7 TVA State Liaison The TVA State Liaison acts as the CECC representative upon dispatch to the State Emergency Operations Center (SEOC) to interpret technical aspects of the emergency condition. He informs the CECC on State problems, requests, and actions.
3.3.8 CECC Plant Assessment Manager The CECC Plant Assessment Manager:
Maintains contact with the SED or Technical Assessment Manager and ensures that necessary support is provided.
Requests assistance from other TVA organizations or Nuclear Steam Supply System (NSSS) vendors as needed.
Provides technical support for planning and reentry/recovery operations.
Ensures the CECC Director is briefed on information pertaining to plant status based upon an assessment of plant status by the CECC and TSC assessment teams.
Ensures that periodic status reports are received from the site and are provided to the CECC Director and other TVA support organizations.
Makes recommendations to the SED on actions to be considered by the site to mitigate the problem based upon the assessment of plant status by the CECC Plant Assessment Team.
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The CECC Plant Assessment Manager is assisted by a Plant Assessment Team and additional support personnel who develop ongoing assessments of facility status and provide additional resource support.
3.3.9 Plant Assessment Coordinator The Plant Assessment Coordinator coordinates the plant status assessment activities in the Plant Assessment Area and directs overall plant assessment function and reports results to the Plant Assessment Manager. The plant information needed by the coordinator and plant assessment team is provided by a continuous telephone communications hookup with plant emergency staff.
3.3.10 CECC Plant Assessment Team The CECC Plant Assessment Team:
Coordinates the decision to activate the Joint Information Center (JIC) with the CECC Director, the Director, Public Relations & Corporate Information, and SEOC if offsite officials elect to activate the SEOC.
Provides a periodic evaluation of plant status information for input back to the TSC and the CECC Plant Assessment Manager. Members of the CECC Plant Assessment Team draw upon their knowledge of plant information, procedures, core damage assessment, and industry analysis to evaluate the assessments provided by the site in terms of current and long-range plant conditions. Results of evaluations and independent assessments provide the data needed for developing any necessary onsite protective actions. Serves as an engineering/operations/core damage assessment consultant for the plant and replies to plant inquiries based on the available information.
Ensures that appropriate safety parameters are selected for trending and the CECC trend boards are maintained.
Maintains a detailed log of the sequence of events during the emergency. Assists the CECC with other site-related communication needs, as necessary.
3.3.11 Resource Support Coordinator The Resource Support Coordinator maintains communications with other TVA Nuclear technical personnel to coordinate support as necessary; coordinates support from other TVA organizations such as legal, medical, finance, and procurement; and coordinates requests for support from other organizations outside TVA such as equipment vendors and INPO.
Coordinates arrangements for special equipment and supplies.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 3.3.12 Engineering Representative The Engineering Representative provides a point of contact in the CECC for onsite and offsite engineering and provides engineering support as needed.
3.3.13 Public Information Manager The Public Information Manager:
Coordinates the decision to activate the Joint Information Center (JIC) with the CECC Director; the Director, Public Relations & Corporate Information; and SEOC if offsite officials elect to activate the SEOC.
Ensures the JIC Spokesperson and the JIC Information Staff are provided information to inform the public and news media in response to an emergency.
Informs the CECC Director of TVA public information activities in response to an emergency.
Coordinates news release drafts with the State and federal agencies participating at the JIC and secures approval of the CECC Director prior to making a release to the media.
Coordinates the decision to establish the JIC with the SEOC.
Directs the activities of support personnel who develop public information and maintain information flow into and from the JIC.
3.3.14 JIC Liaison The JIC Liaison contacts responding agencies and transmits information for coordination, and establishes and maintains an information flow from the JIC or Site Communications to the CECC.
3.3.15 Public Information Writer The Public Information Writer gathers information from the CECC personnel and Technical Advisor, prepares written statements based on that information, and develops information releases to be approved by the CECC Director for release to TVA employees.
3.3.16 Radiological Assessment Manager The Radiological Assessment Manager (RAM):
Ensures that the CECC Director is briefed on matters concerning radiological conditions.
Provides consultation, technical assistance, and obtains additional services as may be required for plant Rad Protection and environmental radiological surveys.
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Ensures that radiological monitoring is conducted in the environment for areas potentially affected by the emergency and evaluates the radiological information to determine the extent of actual or probable hazard to the environment.
Responsible for radiation dose management, including emergency dose authorizations, for personnel under their direction and control.
Provides technical support to the CECC Director.
The RAM directs the activities of support personnel who coordinate collection and evaluation of radiological assessment data in the environs surrounding the facility.
3.3.17 Radiological Assessment Coordinator The Radiological Assessment Coordinator (RAC):
Coordinates dose assessment, environs, and meteorological assessment activities in the Radiological Assessment Area (RAA) located in the CECC.
Directs the overall RAA function and communicates assessment results to the RAM.
Ensures that information is provided to the TSC on dose projections, environs measurements, and meteorological conditions.
Coordinates requests for additional Rad Protection equipment and personnel.
3.3.18 Environmental Assessor The Environmental Assessor:
Coordinates requests for additional Rad Protection equipment and personnel.
Performs monitoring and assessment activities for the TVA environs and coordinates the TVA field monitoring effort with the appropriate State agency regarding field monitoring activities.
Coordinates the analysis of environs samples with the Western Area Radiological Laboratory (WARL).
Provides technical support for planning and reentry/recovery operations.
Coordinates with Dose Assessor regarding the results of the environmental assessments.
Provides environmental monitoring results to the RAC or RAM.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 3.3.19 Dose Assessor The Dose Assessor initiates and performs dose assessment activities during the radiological emergency and during the recovery and reentry phase; coordinates with the Environmental Assessor regarding the predicted position, exposure levels, concentrations, and duration of radiological effluents; and provides dose assessment results to the RAC or RAM.
3.3.20 Meteorologist The Meteorologist:
Coordinates the analysis of environs samples with the Western Area Radiological Laboratory (WARL).
Evaluating meteorological data and developing forecasts which may be used for dose assessment and other emergency preparedness activities.
Reviews adequacy of observed data and replaces missing or invalid observations.
Makes forecasts of dispersion conditions that affect radiological effluents.
Provides dispersion knowledge to dose assessment staff.
Prepares other meteorological forecasts needed for emergency preparedness activities.
3.3.21 Technical Advisors Technical Advisors provide technical assistance and explanation to the State Communicator, Public Information Staff, and Public Information Manager to ensure accurate information is released to the public and State agencies.
3.3.22 Boardwriter(s)
Boardwriters maintain the CECC Status Boards with current information.
3.3.23 Management Services Management Services (MS) makes arrangements for and provides for clerical support, food and water, sanitary facilities, TVA transportation services, lodging, specialized equipment and supplies, communications, drawings, and controlled documents. MS is also authorized to issue checks for payment for emergency services to outside firms.
3.3.24 Local Support TVA maintains agreements with police departments, fire departments, ambulance services, and hospitals near the CRN Site to provide appropriate services as requested.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 3.3.25 Federal Agency Support TVA maintains an agreement with DOE Radiation Emergency Assistance Center/Training Site (REAC/TS), Oak Ridge, Tennessee. Other federal support would be requested through the NRF.
3.3.26 Vendor Support TVA may obtain technical support from the NSSS vendor during emergency situations. TVA may procure other vendor support as needed.
3.3.27 INPO TVA maintains an agreement with INPO, a consortium of nuclear utilities and other nuclear industries, to obtain any necessary support available from the industry during an emergency.
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Federal Agency Support Central State and Local (Nuclear Regulatory Emergency Support (Emergency Commission /
Control Center Operations Centers) Department of Homeland Director1 Security)
Emergency Duty Officer /
Directors Aide Emergency Preparedness Staff Representative(s)1 TVA Liaison to State Management Services Emergency Supervisor Operations Center Clerical Staff Operations Technical Advisors Duty Specialist Plant Public Site Radiological State Assessment Information Senior Vice Emergency Assessment Communicator1 Manager1 Manager President Director Manager1 Plant Joint Assessment Information Coordinator Center Liaison Technical Rad Assessment Support Coordinator Center Plant Information Assessment Writers Operations Team Environs Support Assessor Center Resource Support Coordinator Meteorologist Dose Assessor1 1
These Offsite Emergency Organization positions will be staffed within a prescribed time following an Alert or higher emergency declaration at the CRN Site. The prescribed time will be addressed in the CRN Site COLA.
Figure 3-1 Offsite Emergency Organization 15 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 4.0 EMERGENCY CONDITIONS 4.1 CLASSIFICATION SYSTEM TVA utilizes the following emergency classifications:
Notification of Unusual Event (NOUE)
Alert Site Area Emergency General Emergency This system of classification is consistent with the systems used by State and local emergency organizations. The emergency classifications are graded according to severity and immediate actions are taken to cope with the situation. Escalation to a higher class, or termination, occurs during the course of an emergency if warranted by conditions. Examples of plant conditions and their recommended emergency classes are given in the CRN-EPIPs. These procedures also specify the initial prompt notifications, and information to be provided to State and local emergency organizations. Examples of Initiating Conditions (ICs) and specific instrument readings, if appropriate for the various classifications, are provided in the EPIPs.
NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, provides definitions of the emergency classifications. Not all elements of the definitions apply to SMR technology. These differences are addressed in the following sections.
4.1.1 NOUE This classification provides early and prompt notification of events that are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring response or monitoring are expected unless further degradation of safety systems occurs.
The purposes of the NOUE are: (1) to ensure that the first steps in activating emergency organizations have been carried out; and (2) to provide current information on the unusual event.
TVA maintains the NOUE classification until closeout or escalation to a higher class. TVA notifies the State authorities and the NRC. The State notifies the local authorities. Following closeout, TVA provides a briefing to State authorities. TVA provides a written summary of significant events to the State no later than the next working day.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 4.1.2 Alert An Alert classification is indicated when events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of Hostile Action. Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guides (PAG) exposure levels.
The purposes of the Alert classification are: (1) to ensure that emergency personnel are readily available to respond if the situation becomes more serious or to perform confirmatory radiation monitoring, if required; and (2) to provide offsite authorities current status information.
TVA maintains the Alert class until event termination or escalation to a higher class. TVA notifies the State authorities and the NRC. The State notifies the local authorities. Following closeout, TVA provides a briefing to State authorities. TVA provides a written summary of significant events to the State no later than the next working day.
4.1.3 Site Area Emergency A Site Area Emergency is indicated when events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or Hostile Action that results in intentional damage or malicious acts: (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA PAG exposure levels beyond the site boundary.
The purposes of the Site Area Emergency classification are: (1) to ensure that emergency response centers are staffed; (2) to assure that monitoring teams are dispatched; (3) to assure that personnel required for evacuation of near-site areas are at duty stations if the situation becomes more serious; and (4) to provide current information for, and consultation with, offsite authorities and the public.
TVA maintains the Site Area Emergency classification until event termination or escalation to a higher class. TVA notifies the State authorities and the NRC. The State notifies the local authorities. Following closeout, TVA provides a briefing to State authorities. TVA provides a written summary of significant events to the State no later than the next working day.
4.1.4 General Emergency A General Emergency is indicated when events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or Hostile Action that results in an actual loss of physical control of the facility. Due to the SMR design, releases are not expected to exceed EPA PAG exposure levels offsite.
The purposes of the General Emergency classification are: (1) to initiate predetermined protective actions for the public; (2) to provide continuous assessment of information from the site and offsite; and (3) to initiate additional measures as indicated by releases or potential releases of radioactivity.
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TVA maintains the General Emergency until event termination. TVA notifies the State authorities and the NRC. The State notifies local authorities unless the initial classification is General Emergency, in which case TVA initially notifies the local authorities. Following closeout, TVA provides a briefing to State authorities. TVA provides a written summary of significant events to the State no later than the next working day.
4.2 IDENTIFICATION OF EMERGENCY CLASSES TVA uses a variety of methods to identify emergency situations and to categorize them. As indicated in the CRN-EPIPs, emergencies can be caused by natural disasters such as tornadoes or floods, hazards such as aircraft crashes, releases of toxic gases, or breaches of plant security, as well as by conditions involving plant systems directly.
Recognition of the emergency class is primarily a judgment matter for plant personnel. The ICs used for recognizing and declaring the emergency class are based on specific measurable values or observable conditions defined as Emergency Action Levels (EALs). These can be combinations of specific instrument readings (including their rates of change), annunciator warnings, time periods certain conditions exist, etc. The instrument readings and parameters required for determination of these EALs are detailed in the CRN-EPIPs. TVA uses these EALs as thresholds for determining the emergency classifications. The EALs are reviewed annually by the State.
TVA maintains the capability to assess, classify, and declare an emergency condition within 15 minutes after the availability of indication to plant operators that an emergency action level has been exceeded and to promptly declare the emergency condition upon identification of the appropriate EAL.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 5.0 EMERGENCY NOTIFICATION AND ACTIVATION OF PLAN Emergency measures are developed to aid in the mitigation of emergency conditions.
Emergency measures begin with the declaration of an emergency class and activation of associated emergency organizations. These measures, which will include actions for assessment, correction, and protection, are described in general terms for each emergency class in the following parts of this section. Details of these emergency measures will be found in the appropriate sections of the CRN-EPIPs.
When the Plan is activated, TVA initiates certain predetermined actions. Notification is carried out as shown in Figure 5-1 to alert emergency staff personnel to handle the emergency situation.
5.1 ONSITE Upon detection of a known or suspected emergency, the SM on-duty will utilize a CRN-EPIP to determine the classification of the emergency. After determining the classification of the emergency, the SED will initiate the appropriate procedures referenced by the CRN-EPIP. Each procedure referenced by the CRN-EPIP gives specific instructions on staffing the TSC and the OSC and for notifying appropriate State authorities, the ODS, and the NRC.
5.2 OFFSITE Implementing procedures are provided to activate TVA and State emergency staffs. Essential emergency positions are covered on a 24-hour-a-day basis by duty personnel. Emergency response facilities are located to ensure rapid and effective response of personnel.
5.2.1 NOUE Upon declaration of this classification, TVA initiates the following actions:
A. The Control Room notifies and relays the information to the State within 15 minutes of declaration of the event. TVA utilizes a dedicated ring-down phone to make this notification. TVA utilizes an available commercial telephone line as a back-up method in the event the dedicated circuit is unavailable.
B. The Control Room notifies the NRC immediately after notifying the State but not later than one hour after the emergency declaration is made.
C. The ODS in Chattanooga is notified of the event by the Control Room and records the details of the event in accordance with the appropriate EPIP.
D. The ODS notifies and relays the information to the EDO and CECC Director.
E. The EDO keeps the CECC Director and the Public Information Manager informed of the situation as necessary.
F. The Public Information Manager notifies the Site Communications Consultant, Director, Public Relations & Corporate Information, and the TVA News Bureau (Knoxville).
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G. The SED augments plant on-shift personnel as necessary to initiate corrective actions.
5.2.2 Alert Upon declaration of this classification, TVA initiates the following actions:
A. Notifications outlined in Subsection 5.2.1 are performed.
B. The CECC is staffed.
C. Environmental sampling teams may be dispatched.
D. The TSC and the OSC are activated.
E. The situation is analyzed and any appropriate corrective or preventive actions are initiated.
F. Hourly, or more often as necessary, the State agencies are updated through the CECC on appropriate plant status and environmental conditions as follows:
- 1. Classification of emergency.
- 2. Type of actual or projected release (airborne, waterborne, or surface spill) and estimated duration/impact times.
- 3. Estimate of quantity of radioactive material released or being released and the height of release.
- 4. Chemical and physical form of released material, including estimates of the relative quantities and concentration of noble gases, iodines, and particulates.
- 5. Prevailing weather (wind velocity, direction, temperature, atmospheric stability data, and form of precipitation, if any).
- 6. Actual or projected doses at site boundary.
- 7. Estimate of any surface spill radioactive contamination.
- 8. Emergency response actions underway.
- 9. Request for any needed onsite support by offsite organizations.
- 10. Prognosis for worsening or termination of event based on plant information.
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G. The JIC may be activated.
H. Periodic media releases are provided.
I. The SED augments plant on-shift personnel, as necessary, to initiate corrective actions.
5.2.3 Site Area Emergency Upon declaration of this classification:
A. Each of the actions outlined in Subsection 5.2.2 are performed.
B. Personnel knowledgeable of plant systems may be dispatched to the SEOC if determined appropriate by the CECC Director and if offsite officials elect to activate the SEOC.
C. Sufficient information relative to the plant status, radiological impacts, and protective measures is made available to government officials to enable them to implement ad hoc protective measures (in accordance with a CEMP) for the protection of the public should they be determined appropriate by offsite officials.
D. The JIC is activated.
5.2.4 General Emergency Upon declaration of this classification:
A. Each of the actions outlined in Subsection 5.2.3 are performed.
B. If this is the initial classification, the Control Room notifies the local government agencies within 15 minutes. Performance of Subsection 5.2.2, Step 6, enables government officials to implement ad hoc protective measures for protection of the public per a CEMP should they be determined appropriate by offsite officials.
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Site Emergency Director (Control Room)
Operations Nuclear State / Local Duty Regulatory Government(s)1 Specialist Commission Public Emergency Emergency Information Management Duty Officer Manager Organization 1 The Control Room also notifies the local government(s) if the initial classification is a General Emergency.
Figure 5-1 Chains of Notification 22 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 6.0 COMMUNICATIONS The radiological emergency communications network consists of the EP telephone system, the EP notification system, and the EP radio system. These systems are designed to complement each other in the overall plan for REP communications.
The communications facilities described in the following sections are integrated with the requirements for communications to local and State response organizations. TVA conducts testing of these systems in accordance with established procedures.
6.1 EP TELEPHONE SYSTEM The EP telephone system includes communications equipment installed at the CRN site and the CECC, a number of leased commercial circuits, and privately-owned circuits connecting the CRN Site to the required locations.
6.2 PLANT TELEPHONE SWITCHING EQUIPMENT The telephone switching equipment installed at the CRN Site consists of one or more switching centers equipped with fully redundant common logic and redundant power sources. The majority of plant telecommunications services are served from this switching equipment.
6.3 PLANT OR BUILDING LOUDSPEAKER PAGING This system(s) may be accessed from the plant telephone system and is used for normal plant operations (plant paging) and to instruct and notify personnel during an emergency.
6.4 OFFSITE TELEPHONE COMMUNICATIONS The offsite communications network is used to communicate with federal, State, and other supporting agencies. Access to these agencies is provided through several redundant, diverse routes. This diversity provides offsite routing through more than one type of facility. These facilities include, but are not limited to, commercial facilities such as central office trunks, tie-lines and digital services, plus privately owned and maintained microwave and fiber-optic systems. The offsite telecommunications network is designed to facilitate traffic in the most fail-safe manner to the emergency response organizations.
Telecommunications services are provided between the following locations in a redundant, diverse manner:
CECC to State Emergency Management Agencies.
CECC to the CRN Site.
State Emergency Management Agencies to County Emergency Management Agencies.
In addition to the above listed emergency organizations, the following emergency response facilities are also equipped with public telephone lines:
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JIC(s).
Field Coordination Center(s).
ENS and HPN (NRC FTS 2000 System) telephones provide communications from the TSC, Control Room, and the CECC to the NRC Headquarters and regional offices. TVA performs testing of these telephones on a monthly basis.
6.5 EP NOTIFICATION SYSTEM The EP notification system is an automated system which is used to notify key personnel during nuclear emergencies. The EP notification system has provisions to periodically monitor its own performance to detect and report equipment failures.
6.6 TVA ENTERPRISE EMERGENCY NOTIFICATION SYSTEM The TVA Enterprise Emergency Notification System (TEENS) is a hosted Emergency Management Organization notification system that notifies Emergency Management Organization personnel by contacting devices such as assigned office, mobile, and home telephones, work e-mail, and assigned pagers.
6.7 EP RADIO SYSTEM The EP radio system is a VHF mobile radio system which provides redundant radio coverage. It provides radiological monitoring vehicles with mobile communications to other vehicles and to the following locations:
Radiation Protection.
TSC.
Control Room.
CECC in Chattanooga.
6.8 OTHER RADIO COMMUNICATIONS There is an in-plant repeater system utilized by Nuclear Security Services which enables transmission without interruption to various areas of the plant. A separate radio located in the plant Central Alarm Station (CAS) is a direct link to the local law enforcement agency (LLEA) officials. The plant ambulance has a radio used for communication with the local hospitals and the plant. Portable two-way radios are available for additional site communications.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 7.0 PUBLIC INFORMATION AND EDUCATION 7.1 PURPOSE The purpose of the TVA emergency public information and education program is to ensure timely distribution of accurate information during an emergency in accordance with one or more applicable EPIPs. The program also provides for TVA to coordinate emergency information with non-TVA agencies that have a primary response role prior to its release to the public or news media. The program provides for a JIC to be established for use during an emergency. The purpose of the JIC is to provide a single location for TVA, local, State, and federal agencies to coordinate public information activities. TVA and the State conduct coordinated annual orientations to acquaint the local area news media with the emergency plans, radiological information, and points of contact for release of information in an emergency.
7.2 RESPONSIBILITIES 7.2.1 CECC Director The CECC Director or delegate is responsible for approving written news statements after the CECC is activated.
7.2.2 JIC Spokesperson The JIC Spokesperson is responsible for representing TVA during news briefings and coordinating information with other federal, State, and local spokespersons prior to the briefings.
7.2.3 Director, Public Relations & Corporate Information Director, Public Relations & Corporate Information is responsible for directing emergency public information activities of the agency in accordance with approved procedures. This includes the responsibility for coordinating with the CECC Director and non-TVA agencies, who would participate in JIC activities, in determining when to activate or deactivate the JIC.
7.2.4 Operations Communications Operations Communications is responsible for the development, implementation, and maintenance of nuclear public information organizations and activities for an emergency, as well as those nuclear public information programs conducted on an annual basis.
7.3 PUBLIC INFORMATION FACILITIES Public Information personnel are present at three locations with sufficient staff available to maintain operations on a 24-hour basis: (1) Operations Communications directs the activities of the emergency public news media present at the site; (2) the CECC in the Chattanooga Office Complex where staff will develop news releases and coordinate the news releases with offsite agencies; and (3) the JIC where staff coordinates with the offsite agencies in presenting emergency news briefings and respond to public telephone inquiries.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 7.4 COORDINATION OF INFORMATION Prior to activation of the CECC, coordination of public information with non-TVA primary response agencies is handled through Operations Communications in accordance with emergency public information procedures. Upon activation and staffing of the CECC, the responsibility for coordination of public information with non-TVA agencies shifts to the CECC Information Staff. Upon activation and staffing of the JIC, the responsibility for coordination of public information shifts from the CECC to the JIC emergency response staff when and if offsite agencies are also operational at the JIC. The CECC Director continues to approve written news statements. Non-TVA primary response agencies are provided copies of written news statements until they are available to support coordination in the JIC.
7.5 PUBLIC EDUCATION TVA coordinates development and distribution of public education materials and programs with the appropriate State agency.
7.6 EMPLOYEE COMMUNICATIONS An information system that employees can access provides a method of informing TVA employees who do not have emergency response assignments about an emergency.
7.7 RUMOR CONTROL/PUBLIC INFORMATION Teams in the JIC are responsible for emergency information. In the JIC, a trained media relations team responds to news media inquiries by telephone and media briefing and a trained information team responds to citizen telephone inquiries. Also in the JIC, a trained media monitoring team monitors news media coverage. TVA coordinates information activities with offsite agencies at the JIC.
7.8 TRAINING TVA provides initial training and annual retraining to emergency public information staff to allow them to respond.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 8.0 EMERGENCY RESPONSE FACILITIES, EQUIPMENT, AND SUPPLIES 8.1 NUCLEAR SITE FACILITIES 8.1.1 Technical Support Center The CRN Site has a Technical Support Center (TSC) which is dedicated for use during an emergency. Once activated, the TSC is the focal point of onsite activity and is the primary source of communication from the site with offsite organizations during the event. The TSC has sufficient staff to provide management control of the site response to the event. Equipment is available to enable the TSC staff to communicate with onsite and offsite TVA emergency personnel. An area within the TSC is dedicated for NRC use which includes commercial telephones and the NRC FTS 2000 System telephones. Sufficient plant parameter information is available to the TSC to enable the TSC staff to assess the consequences of an event and assist the Control Room personnel in mitigating the emergency.
The TSC is activated during radiological emergencies in accordance with CRN-EPIPs. The degree of activation varies depending upon the emergency class. Additional information regarding the TSC is provided in Appendix A.
8.1.2 Operations Support Center The CRN Site has an Operations Support Center (OSC) which is a pre-designated area for the assembly of personnel to support the Control Room Operations crew during an emergency. The OSC area(s) is under the control of the SED in the Control Room until the TSC is staffed and will provide damage assessment, maintenance and repair services, and necessary technical services. Communications are available with the TSC. The OSC also establishes and maintains appropriate communications with any teams that may enter the plant for assessment or repair.
Respiratory protective devices, protective clothing, portable lighting, other protective equipment and tools are available in the OSC, as needed.
The OSC is activated during radiological emergencies in accordance with CRN-EPIPs. The degree of activation varies depending upon the emergency class. Additional information regarding the OSC is provided in Appendix A.
8.1.3 Local Recovery Center The CRN Site has a Local Recovery Center (LRC) which is a pre-designated facility dedicated for use by offsite TVA and NRC personnel that may be assigned to the CRN Site for recovery operations. In addition, the LRC may be used by the NRC during the event as an area near the site for assessment and assistance and has the capability to communicate offsite. Personnel in the LRC have access to necessary drawings and documents. Meteorological information is available in the LRC. The LRC may serve as an alternate emergency response facility, as needed, and during an emergency, may be used as a staging location for personnel prior to dispatch to the CRN Site. Additional information regarding the LRC is provided in Appendix A.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 8.1.4 Site Decontamination Facilities The CRN Site has facilities for the decontamination of personnel including those with injuries.
Information on these facilities is provided in Appendix A.
8.1.5 Equipment, Supplies, and Supplemental Data The CRN Site has sufficient equipment and supplies for the operation of the site emergency response facilities. Additional seismic and hydrological information can be obtained by the CECC from other TVA nuclear plants or the TVA water quality organization. Reference Appendix A, Attachment 2 for additional information regarding emergency equipment and supplies.
8.2 CENTRAL EMERGENCY CONTROL CENTER The purpose of the Central Emergency Control Center (CECC) and associated CECC staff is to provide the facilities and manpower for evaluating, coordinating, and directing the overall activities involved in coping with a radiological emergency. The specific response time for staffing the CECC will be determined as a result of evaluating the specific accident sequences and included in the COLA.
During an emergency, the CECC Director and staff will review the response to the emergency by TVA to ensure an effective response. Additionally, the CECC Director and staff ensure that appropriate information is communicated to government officials.
The CECC staff coordinates with the other TVA emergency response facilities to ensure an effective TVA effort in response to an emergency situation. The CECC staff also provides an accurate description of the emergency situation for TVA management and public information. In addition, the CECC coordinates with offsite federal agencies, such as NRC and DOE, to ensure availability of additional outside resources to TVA.
The CECC is located in the northeast corner of the sixth floor of Lookout Place in the TVA Chattanooga Office Complex (COC) in Chattanooga, Tennessee. It is designed to house the CECC Director and staff during an emergency situation. Included in the CECC are areas for the Plant Systems Assessment, Radiological Assessment, and Public Information Staff. A floor plan for the CECC is provided in Figure 8-1. Access control to the CECC is provided by Security personnel.
The CECC is designed to serve as the central point for information collection, assessment, and transfer during an emergency. The CECC is provided with direct communication links with State emergency response centers, other TVA emergency response organizations, other TVA nuclear plant sites, the JIC, and offsite federal and State organizations.
The CECC is activated during radiological emergencies in accordance with CRN-EPIPs. The degree of activation varies depending upon the emergency classification. of this Plan provides additional description of and justification for the location of the CECC.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 8.3 RADIOLOGICAL MONITORING CONTROL CENTER The Radiological Monitoring Control Center (RMCC) is located in the Tennessee Emergency Management Agency East facility (TEMA East) in Knoxville, Tennessee. If it is deemed necessary by TEMA East for an emergency at the CRN Site, the RMCC will be staffed by the TVA Field Coordinator and personnel from the State in an ad hoc manner consistent with the CEMP approach. TVA will be co-located in the RMCC and coordination of TVA and State monitoring teams will be conducted from that point. Environmental monitoring data will be shared between the State and TVA. These personnel cooperate in providing direction and control of the monitoring teams.
Monitoring teams have maps of the area and are directed to selected monitoring points or locations to collect data. This data is transmitted to the RMCC and CECC for analysis.
Facilities at the RMCC include radio and telephone communications, and necessary desks, tables, and chairs.
8.4 JOINT INFORMATION CENTER The CRN Site has a Joint Information Center (JIC) established near the site to assist the news media in providing press coverage during an emergency. The location, function, and capabilities of the CRN Site JIC is addressed in the CRN Site COLA.
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Figure 8-1 Central Emergency E y Control C Center 30 Revission 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 9.0 ACCIDENT ASSESSMENT 9.1 ONSITE In-plant accident assessment actions are carried out by the plant emergency staff in order to properly characterize and classify the emergency, determine the actual or potential radioactivity releases, and determine the effect on plant personnel.
Assessment methodology consists of actions carried out through plant operating procedures as well as CRN-EPIPs. At the onset of an emergency, plant operating procedures (normal, abnormal, and emergency) assist the plant operator and SED in identifying the cause of the emergency, actions necessary to control the emergency, radioactivity release rate, if any, and in-plant radiation levels. The CRN-EPIPs assist the SED in: (1) identifying and reassessing emergency classification; (2) determining the need for plant area evacuation; (3) initiating activation of onsite emergency organizations; (4) directing the utilization of needed medical and/or decontamination facilities; and (5) implementing predetermined security and access control plans.
Each of the above-mentioned activities is described within the plant operating procedures or CRN-EPIPs, as applicable, for a given situation. The distinct breakdown of assessment actions into operating procedures and implementing procedures is necessary since some assessment actions are necessarily carried out prior to identification or classification of an emergency. The procedures to ensure that emergencies are properly evaluated, timely notifications are made, and assessment and onsite protective actions are performed, are compiled in the CRN-EPIPs.
These procedures are summarized by topic in Appendix A, Attachment 1.
Under severe emergency conditions, and as required by the plant emergency operating procedures, the onsite Emergency Management Organization is responsible for recognition of severe emergency conditions, transition to, and implementation of the Severe Accident Management Guidelines (SAMGs).
9.2 OFFSITE 9.2.1 General Information TVA maintains the capability to assess the consequences of potential or actual releases of radioactivity offsite. If determined appropriate by State and local agencies, protective actions for the protection of the public may be implemented using an all hazards approach to emergency planning.
Implementing procedures have been developed for the CECC to ensure that emergencies are properly evaluated, timely notifications are made, and assessment and onsite protective actions are performed. Once an SMR technology is selected, the details on staffing levels, response times, and accident progression rates will be known and can then be reflected in a set of EPIPs similar to the following list:
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CECC-EPIP-1-CENTRAL EMERGENCY CONTROL CENTER OPERATIONS CECC-EPIP-2-OPERATIONS DUTY SPECIALIST PROCEDURE FOR NOTIFICATION OF UNUSUAL EVENT CECC-EPIP OPERATIONS DUTY SPECIALIST PROCEDURE FOR ALERT, SITE AREA EMERGENCY, OR GENERAL EMERGENCY CECC-EPIP-4-NOT ACTIVE AT THIS TIME CECC-EPIP-5-NOT ACTIVE AT THIS TIME CECC-EPIP CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY CECC-EPIP CECC RADIOLOGICAL ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY CECC-EPIP DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES CECC-EPIP-9-EMERGENCY ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURES CECC-EPIP-10-NOT ACTIVE AT THIS TIME CECC-EPIP-11-SECURITY OF OFFSITE EMERGENCY RESPONSE FACILITIES CECC-EPIP-12-OPERATIONAL READINESS CHECK OF THE CECC AND THE FIELD COORDINATION CENTERS FOR SQN, BFN, WBN & CRN AND JOINT INFORMATION CENTERS (JIC)
CECC-EPIP-13-NOT ACTIVE AT THIS TIME CECC-EPIP-14-NUCLEAR EMERGENCY PUBLIC INFORMATION ORGANIZATION AND OPERATIONS CECC-EPIP EP FIELD SUPPORT STAFF RADIOLOGICAL EMERGENCY PROCEDURE CECC-EPIP TERMINATION AND RECOVERY CECC-EPIP CENTRAL EMERGENCY CONTROL CENTER METEOROLOGIST PROCEDURES CECC-EPIP-18-TRANSPORTATION AND STAFFING UNDER ABNORMAL CONDITIONS 32 Revision 1
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CECC-EPIP POST EMERGENCY FUEL DAMAGE ASSESSMENT CECC-EPIP NOT ACTIVE AT THIS TIME CECC-EPIP EMERGENCY DUTY OFFICER PROCEDURE FOR NOTIFICATION OF UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY CECC-EPIP OPERATIONS DUTY SPECIALIST TRANSPORTATION INCIDENTS INVOLVING A SHIPMENT OF RADIOACTIVE MATERIAL CECC-EPIP RADIOACTIVE MATERIAL TRANSPORTATION INCIDENTS 9.2.2 Sampling Team TVA has vehicles equipped to monitor the environment for radioactivity. Each vehicle has an air sampler, radiation measurement equipment, a generator, radio, and other assorted equipment.
A detailed listing of the minimum required equipment is available in the CECC-EPIPs.
These vehicles are dispatched for environmental monitoring for Site Area Emergency and General Emergency classifications. TVA may deploy these vehicles for the NOUE and Alert classifications, if warranted. One or more vehicles is stationed at the CRN Site.
Each sampling team has the capability to:
Obtain environmental samples for analysis.
Make direct radiation readings.
Collect air samples and analyze them for gross beta-gamma radioactivity over a range of energies.
Collect air samples and analyze them for radioiodine in the field, to concentrations as low as 10-7 microcuries/cc.
CRN-EPIPs describe the composition and activation of sampling teams.
For the Site Area Emergency and General Emergency classifications, teams are dispatched from the nearest location. Teams may be deployed for the NOUE or Alert, if warranted. If necessary, TVA can coordinate team transport via helicopter or fixed-wing aircraft.
The TSC Rad Protection Manager or CECC Environs Assessor can request assistance from a neighboring plant for environmental monitoring, if deemed necessary.
TVA has aquatic monitoring teams located at Chattanooga, Tennessee, and Knoxville, Tennessee. These teams have boats that can be deployed to obtain samples from the river for subsequent analysis for radioactivity in the laboratories.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 9.2.3 Analyzing Environmental Samples The sampling teams may send samples to the WARL for analysis. The WARL has the capability to perform further quantitative and qualitative analysis. The WARL is available as needed and can be operated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. The WARL can establish a central point for receipt of samples when needed.
9.2.4 Meteorological Information 9.2.4.1 Primary Meteorological Measurements TVA has developed the meteorological measurements program to conform to the intent and guidance of Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants (RG 1.23). Wind direction, wind speed, and air temperature are measured at two levels.
The temperature difference is used to estimate the Pasquill stability class. Precipitation and dew point temperature are also measured. Hourly and 15-minute average meteorological data from the plant Environmental Data Station are available to the CECC, TSC, State, and LRC. More specific information on the meteorological measurements program can be found in Section 2.3 of the CRN SSAR.
9.2.4.2 Backup Meteorological Data Estimation Procedures TVA has prepared objective backup procedures to provide estimates for missing or garbled data needed to perform dose calculations and to determine transport estimates. They incorporate available onsite data. Each procedure has an accompanying statement of reliability.
9.2.4.3 Real Time and Forecast Meteorological Data The CECC Meteorologist has the responsibility for providing meteorological information to CECC Staff. The dose assessors use this meteorological information to project doses. The meteorological support actions and projection of doses are discussed in detail in CECC-EPIPs.
Meteorological support may be provided in the CECC or from a remote location.
9.2.4.4 Remote Access of Meteorological Data Access of up to the most recent 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of 15-minute and hourly meteorological data is available to authorized users through the CECC computer. The remote access system gathers data from the CRN Site, performs unit conversion, reformats data, and flags questionable values.
9.2.5 Dose Assessment On-shift dose assessment capability is maintained at the CRN Site, and can be implemented (if needed during the initial phase of an emergency) until the CECC is activated and assumes the dose assessment function.
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Doses from emergency-related releases of radioactivity are estimated using a combination of calculations, field measurements, and laboratory analyses of environmental samples. Using plant operational data, field measurements, and effluent monitor readings, actual or potential releases of radioactivity are analyzed by the plant staff, the Radiological Assessment staff, or the CECC Plant Assessment Team to generate or modify a source term for use in the dose assessment.
With this information, the CECC dose assessment team can predict doses through the use of several models and/or methods described in the CECC-EPIPs. These models provide a means of estimating personnel exposures throughout the emergency and recovery period. Environs measurements are used, to the extent possible, to confirm doses projected by modeling.
A preliminary dose projection is performed following receipt of measured effluent release data (the source term) and meteorological data. The preliminary dose projection is followed up by a more detailed assessment using computerized dose models. Manual dose assessment methods are available for use in the event that the computer is unavailable. Input to the detailed calculations includes measured source terms, projected future releases, near real-time and forecast meteorological data, field measurements of exposure rates and/or airborne radioactivity in the environs around the plant, or a combination thereof. Field measurements are used to estimate doses, and (especially in the case of an unmonitored release) source terms, and to verify doses projected using models.
After termination of emergency-related releases to the atmosphere, integrated doses are calculated to assist in recovery/reentry operations.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 10.0 PROTECTIVE RESPONSE 10.1 ONSITE PROTECTIVE ACTIONS FOR RADIOLOGICAL EVENTS In the event of an unplanned significant release of radioactivity or sudden increase in radiation levels, it is the responsibility of the SED to make the decision concerning the necessity for building and area evacuation. In arriving at this decision, the primary consideration is personnel safety. The SED may use the various radiation and airborne radioactivity monitors placed throughout the plant, with readout in the Control Room, to assess the extent of the radiological hazards and to determine the extent of evacuation necessary.
The assembly/accountability alarm is used to initiate the assembly of site personnel. The public address system is used if only specific areas are to be evacuated. Nuclear Security Services personnel patrol the area between the security boundary described in the Physical Security Plan and the Site Boundary, and evacuate any nonessential personnel.
Upon hearing the emergency alarm, persons in the plant areas proceed to their pre-assigned areas to be accounted for and await further instructions from the SED. The pre-assigned areas are designated in approved procedures. Predetermined assembly areas are identified in approved procedures and radiological surveys are completed as required by the TSC. The number of unaccounted individuals should be available within approximately 30 minutes for persons within the security area as defined in the Physical Security Plan.
If only a particular area is cleared, personnel in that area evacuate to a safe area. An accountability report is provided to the SED from Security. Further details of evacuation procedures are described in CRN-EPIPs.
If radiation levels or airborne radioactivity at an assembly point is significantly higher than alternative assemble areas, or the SED deems it necessary, the SED orders relocation to a safe assembly point. Employees are released from this assembly point when the SED determines it is suitable to do so.
Procedures require that all potentially contaminated people and vehicles pass through a Rad Protection check-point for survey prior to being released.
In the event of the evacuation of nonessential site personnel, the SED notifies the CECC Director. If the personnel require transportation and sheltering, the CECC Director coordinates arrangements with the appropriate State agency. If the evacuees require radiological decontamination, they are informed of transportation, sheltering, and decontamination arrangements prior to leaving the plant site. An alternate decontamination facility is specified in a CRN-EPIP.
Contaminated personnel are decontaminated to the limits specified in the CRN Site Radiological Control Instructions (RCIs) by methods described in the instructions before being released by TVA.
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Procedures also specify the action to be taken by, and the accountability of, personnel having an emergency assignment. Essential plant personnel remaining onsite are protected by plant systems designed to provide a habitable environment even under the most serious emergency conditions or by precautionary measures such as the use of respiratory protective equipment and protective clothing. Personnel doses are controlled in accordance with Section 11.0.
10.2 ONSITE PROTECTIVE ACTIONS FOR HOSTILE ACTION EVENTS A range of protective actions to protect onsite personnel during a Hostile Action event are developed to ensure the continued ability to safely shut down the reactor(s) and perform the functions of the Emergency Plan. This range of protective actions are contained in the CRN Site abnormal procedures. These procedures are classified security sensitive.
10.3 OFFSITE As addressed in the Federal Emergency Management Agencys (FEMA) Comprehensive Preparedness Guide 101, Developing and Maintaining Emergency Operations Plans (CPG-101), if determined appropriate, government officials may utilize a CEMP approach to emergency planning to implement ad hoc protective actions to protect the public.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 11.0 RADIOLOGICAL PROTECTION The Radiological Protection Section at the CRN Site is responsible for Radiological Protection activities onsite. Its function is to develop instructions to implement the requirements of Title 10 Code of Federal Regulations, Part 20, and other required standards as well as the requirements and policies in TVA radiological control procedures. The Section provides surveillance during normal operation as well as emergency situations. In addition, the Section advises key plant personnel on radiological matters for routine and emergency conditions.
The limiting doses to occupational workers during routine plant operations are found in TVA radiological control procedures. If possible, TVA maintains these limits during emergency operations.
If these standards cannot be met during emergencies, TVA implements the dose guidance described in Table 11-1. A CRN-EPIP describes the methods to use and authorizes the doses outlined in Table 11-1. Table 11-2 describes the health effects of radiation doses greater than 25 RAD.
For individuals entering radiation work permit areas, electronic dosimeters and primary dosimeters are issued and read in accordance with the site TVA radiological control procedures. The electronic dosimeters can be read at any time. Primary dosimetry processing and evaluation is performed by an organization currently accredited by the National Voluntary Laboratory Accreditation Program (NVLAP) of the National Institute of Standards and Technology for the type or types of radiation that most closely approximates the type of radiation or radiations for which the individual wearing the dosimeter is monitored. Dose records are maintained on each monitored individual by a computer.
TVA radiological control procedures contain the criteria used to establish contamination zones and to release personnel, equipment, and clothing. Onsite facilities are available to decontaminate equipment and personnel.
Procedures for using individual respiratory protection and protective clothing are provided in specific plant operating procedures. Procedures for the use of radioprotective drugs are provided in the EPIPs. Drinking water and eating controls are established by Radiation Protection.
Authorizations for emergency dose limits for TVA personnel is provided by the SED.
TVA implements adequate protective measures so that dose, considering both internal and external pathways, is maintained As Low As Reasonably Achievable (ALARA). Internal dose is minimized by the use of respiratory protection equipment consistent with maintaining the Total Effective Dose Equivalent (TEDE) ALARA, and protective clothing is used to minimize personnel contamination. If a projected dose to a workers thyroid is expected to exceed 10 rem during a radiological emergency, Potassium Iodide (KI) is issued in accordance with applicable implementing procedures.
Personnel shall not enter any area where dose rates are unknown or unmeasurable with either instruments or available dosimetry.
Receipt of emergency exposures in excess of 10 CFR 20.1201 limits shall be on a voluntary basis.
Personnel receiving emergency exposures shall be informed of the risks involved including the numerical levels of dose at which acute effects of radiation will be incurred, and numerical estimates of the risk of delayed effects. Table 11-2 provides information consistent with Environmental Protection Agency Protective Action Guides and Planning Guidance for Radiological Incidents (EPA PAG Manual), Draft for Interim Use and Public Comment, dated March 2013," which may be useful for this briefing purpose.
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Personnel receiving emergency doses should be restricted from further occupational exposure pending the outcome of exposure evaluations, and, if necessary, medical surveillance.
Any personnel dose in excess of five (5) rem TEDE shall be handled in accordance with the TVA Nuclear Radiological Protection Plan.
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TABLE 11-1 EMERGENCY WORKER DOSE GUIDANCE TEDE Dose Condition 5 rem All, maintain dose ALARA 10 rem Protection of valuable property when lower dose not practicable.
25 rem Lifesaving or protection of large populations when lower dose not practicable.
Greater than 25 rem Lifesaving or protection of large populations when lower dose not practicable.
Only on a volunteer basis to persons fully aware of the risks involved.
NOTE: Situations may occur in which a dose in excess of regulatory limits (10 CFR 20.1201) would be required for plant and lifesaving operations. It is not possible to prejudge the risk that one person should be allowed to take in these situations. However, persons undertaking an emergency mission in which the dose would exceed regulatory limits should do so only on a voluntary basis and with full awareness of the risks involved (EPA PAG Manual, March 2013).
Guidance for dose to the lens of the eye is three (3) times the listed TEDE value. Dose to any other organ (including skin and body extremities) is ten (10) times the listed TEDE value.
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TABLE 11-2 HEALTH EFFECTS OF RADIATION DOSES GREATER THAN 25 RAD I. Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours1.
Whole Body Early Whole Body Prodromal Absorbed Dose Fatalities2 Absorbed Dose Effects3 (rad) (percent) (rad) (percent) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 1 Risks will be lower for protracted exposure periods.
2 Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.
3 Forewarning symptoms of more serious health effects associated with large doses of radiation.
II. Approximate Cancer Risk to Average Individuals from 25 Rem Effective Dose Equivalent Delivered Promptly.
Risk of Premature Death Average year of life Age at Exposure (deaths per 1,000 persons lost if premature death (years) exposed) occurs (years) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11 Note: Tables referenced from the "Environmental Protection Agency Protective Action Guides and Planning Guidance for Radiological Incidents (EPA PAG Manual), Draft for Interim Use and Public Comment, dated March 2013."
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 12.0 MEDICAL SUPPORT 12.1 GENERAL INFORMATION Facilities, equipment, medical supplies, and trained personnel are available for first aid/emergency medical treatment of ill or injured persons onsite.
Guidance for medical assistance is found in a CRN-EPIP. Immediate lifesaving and disability limiting procedures take precedence over noncritical decontamination and dosimetry assessment measures.
When activated, the CECC coordinates the care, disposition, and reporting of injuries known or suspected to be associated with excess levels of radiation exposure or contamination. The purpose of the Medical Emergency Response Team (MERT) (team composition specified in a CRN Site procedure) is to:
Provide first aid/emergency medical treatment for ill or injured persons onsite, including those who may have been exposed to or contaminated with radioactive material.
Minimize injury during the rescue, treatment, and transport of injured persons, while minimizing radiological hazards and exposure to the victim.
Advise and protect attending personnel from unacceptable and unnecessary radiological hazards and exposures.
Identify, document, and control radiation exposure and contamination hazards associated with the emergency.
12.1.1 Classification And Handling Of Medical Emergency Patients 12.1.2 Noncontaminated-Nonirradiated When it is known that the patient is not contaminated and has not been overexposed to radiation, TVA handles the patient according to standard first aid/emergency medical protocol. The patient, ambulance crew, receiving hospital, and attending physician (as applicable) are advised of the absence of radiological complications.
12.1.3 Irradiated-Noncontaminated TVA coordinates the removal of the patient from the source of radiation exposure as soon as medical conditions and essential treatments permit. Continued medical care for physical injuries, including ambulance transport, is provided as indicated. Rad Protection determines and reports radiation exposure levels, including affected body areas. Emergency care for the radiation exposure is governed by the dose assessment and the medical status. Involved personnel are advised of the absence of radiological contamination.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 12.1.4 Contaminated For patients known to be or suspected of being contaminated, TVA coordinates essential first aid and emergency medical care. Decontamination activities are accomplished as the medical status permits.
Involved personnel are advised of the contamination hazard. Continued care and decontamination decisions are made on an individual basis by the responsible medical care provider and Rad Protection.
12.2 TRANSPORTATION OF INJURED PERSONNEL The decision to transport a patient offsite is the responsibility of the emergency medical care provider performing patient assessment, i.e., Emergency Medical Technician (EMT) or Registered Nurse. If conflicting decisions arise, the option which provides the patient with the optimal level of medical care is chosen.
When ambulance transportation is indicated, transport may be provided by either the site Fire Protection EMTs (using a TVA ambulance) or by an agreement ambulance service. The MERT Team Leader coordinates requests for offsite ambulance assistance through the SM. The SM performs initial requests and notifications for assistance.
TVA maintains arrangements for one or more agreement ambulance services for the CRN Site with trained personnel to transport patients, including those who may have been exposed to or contaminated with radioactive material. These services are designated in a CRN-EPIP and letters of agreement for response are maintained. (See Section 16.5.)
12.3 INTERAGENCY ASSISTANCE FROM REAC/TS TVA maintains arrangements with the Radiation Emergency Assistance Center/Training Site (REAC/TS) as the CRN Site receiving hospital. REAC/TS, which is in close proximity to the CRN Site, is a DOE-sponsored facility operated by Oak Ridge Associated Universities Medical and Health Sciences Division in cooperation with the Oak Ridge Methodist Medical Center in Oak Ridge, Tennessee. The University of Tennessee Medical Center in Knoxville, Tennessee serves as a back-up to REAC/TS. Specialized facilities and expert personnel are available at both medical facilities for definitive care for radiation emergency victims. Letters of Agreement for services are maintained. (See Section 16.5.)
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 13.0 TERMINATION AND RECOVERY 13.1 TERMINATION The SM/SED is responsible for the decision to terminate an event for which the onsite and offsite emergency response facilities have not been activated.
In the event of an incident requiring activation of onsite and offsite emergency centers, the SED coordinates the decision to terminate the event with the CECC Director after consultation with the plant technical and operations staffs. This decision is based upon a comprehensive review of plant status and system parameters. These considerations include, but are not limited to, the following:
Stability of the reactor shutdown condition, i.e., successful progress toward a cold shutdown condition Integrity of the reactor containment building Operability of engineered safety systems and decontamination facilities Availability and operability of a heat sink Integrity of power supplies and electrical equipment Operability and integrity of instrumentation including radiation monitoring equipment (also including portable equipment assigned during the emergency)
Availability of trained personnel and support services Control of radiological effluent releases Decisions to relax protective measures for the public that may have been implemented will be made by the appropriate State representatives. The CECC Director provides information to the appropriate State agencies to facilitate the decision. The State has the authority and responsibility for offsite recovery efforts. TVA will provide assistance, as requested, through the recovery organization shown in Figure 13-1 (Figure 13-1 lists functions which must be addressed for recovery; the normal organizational titles may be different than what is represented here).
The CECC Director, after consultation with the State, the SED, and discussion with the NRC (if appropriate), announces that the emergency has terminated and the recovery phase is to be initiated, if appropriate. TVA then develops procedures and plans to implement the most expeditious recovery sequence to return the plant to normal operation.
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Chief Nuclear Officer SVP VP Nuclear CECC Public VP Nuclear SVP VP Nuclear Engineering Operations Information Licensing Operations Oversight
& Support Support Manager Reactor Corporate General Engineering Functional Site Vice Manager,
& Fuels Area Manager: President Quality General Rad Assurance Manager Protection Chemistry Senior Maintenance Manager Work Control Plant Manager Equipment Operations &
Reliability / ENG/Rad Administrative Systems Monitoring Support Engineering Instruments Radwaste &
Program Manager Environmental Mechanical/Nuclear Protection Senior Engineering Design Manager Design Program Manager Engineering Electrical/I&C Engineering Design Senior Program Senior Nuclear Site Manager Manager Security Nuclear Systems Security Engineering Director Site EP Civil/Structural Emergency Manager Engineering Preparedness Electrical/I&C Director Site Engineering Engineering Mechanical
/Nuclear Engineering Figure 13-1, TVA Recovery Organization 45 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 13.2 RECOVERY ORGANIZATION 13.2.1 Chief Nuclear Officer The Chief Nuclear Officer will direct the overall recovery effort. If the recovery phase is expected to be a long-term process, he may form a team to be responsible for continuous control of the recovery operation, thus permitting other personnel to return to their normal duties. The organizational structure of such a team would be contingent upon the emergency situation and procedures required for recovery. The LRC is available to provide additional office space near the site for the recovery team at the discretion of the Chief Nuclear Officer.
13.2.2 Senior Vice President Operations The Senior Vice President Operations is responsible for the onsite recovery effort and for developing required recovery procedures. He requests any needed offsite support through the Site Vice President and/or Plant Manager.
13.2.3 Site Vice President The Site Vice President is responsible for coordinating the onsite efforts with the overall TVA recovery effort. The Site Vice President (SVP) is in charge of the LRC should additional office space be needed.
13.2.4 Vice President, Operations Support The Vice President, Operations Support directs that the Corporate Functional Area Managers provide support in the following areas:
Radiological Protection Chemistry Maintenance Work Control Operations Radwaste & Environmental Protection Emergency Preparedness Nuclear Security Services Eng/Rad Monitoring Instrument Technical support and Environs sampling assistance as requested by the State Dose Assessment 46 Revision 1
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Environmental Monitoring 13.2.5 CECC Public Information Manager The CECC Public Information Manager acts as an interface between TVA and the news media.
Assists the Chief Nuclear Officer in drafting news releases concerning progress of the recovery operation. Coordinates news releases with TVA management and State and federal officials as required. Coordinates press briefings and interviews concerning the incident.
13.2.6 Vice President, Nuclear Licensing The Vice President, Nuclear Licensing provides support in various licensing issues including primary interaction with the NRC.
13.2.7 Vice President, Engineering & Support The Vice President, Engineering & Support provides support in the area of plant components, Reactor Engineering, fuels and in various engineering disciplines.
13.2.8 Vice President, Nuclear Oversight The Vice President, Nuclear Oversight provides Quality Assurance oversight of the recovery process.
13.2.9 Other TVA Resources Other TVA resources plus other governmental and vendor support will be available through the TVA corporate organization to aid the SED in developing, evaluating, and implementing specific site recovery and reentry operations.
13.3 ONSITE RECOVERY Major post-emergency onsite recovery measures are performed in accordance with written procedures. Additional procedures which may be developed following an emergency include the following activities:
The first auxiliary/reactor building entry.
The first containment building entry.
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Test and startup of restored facilities.
Appropriate personnel protective measures are taken on initial entries and throughout assessment and recovery operations to limit exposures to those outlined in Section 11.0.
Reentry and recovery individual and population dose estimates are obtained using dose rate measurements or calculations and population distribution (see Section 9.2.5). The CECC-EPIPs contain this methodology.
13.4 LOCAL RECOVERY CENTER The LRC provides a facility for TVA recovery management as well as NRC emergency response personnel and other emergency and/or recovery personnel. The LRC provides adequate space for TVA and others who may locate there to support the site should additional office space near the site become necessary during the recovery phase. The LRC provides dedicated space for NRC personnel and contains adequate supplies, communications, and data necessary for them to carry out appropriate functions. See Appendix A for the description of the CRN Site LRC.
13.5 OFFSITE RECOVERY As addressed in the FEMA Comprehensive Preparedness Guide 101, Developing and Maintaining Emergency Operations Plans (CPG-101), if determined appropriate, government officials may utilize a CEMP approach to emergency planning to implement ad hoc protective actions to protect the public.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 14.0 DRILLS AND EXERCISES 14.1 DRILLS Drills are conducted to develop and maintain key skills required for emergency response. These drills may be conducted individually or as part of an REP exercise.
The following drills are required:
14.1.1 Medical Emergency Drills A medical emergency drill involving a simulated contaminated/injured individual, with participation by a TVA or agreement ambulance and each agreement hospital (see Section 16.5) is conducted each calendar year for the CRN Site. Scenario development, drill activities, and evaluations are jointly conducted and critiqued by EP and the site.
14.1.2 Radiological Monitoring Drills Environmental monitoring vehicle drills are conducted each calendar year for the CRN Site.
These drills include collection and analyses of sample media (i.e., water, air, grass, and/or soil as may be required by the scenario), direct radiation measurements, operation of vehicles, communication equipment, sampling equipment, and recordkeeping. The scenario is developed and the drills are conducted and critiqued by the site or EP.
14.1.3 Rad Protection Drills Rad Protection drills are conducted twice each calendar year for the CRN Site. These drills involve response to, and analysis of, simulated elevated airborne samples and direct radiation readings in the plant. The scenario is developed and the drills are conducted and critiqued by the site.
14.1.4 Radiochemistry Drills Radiochemistry drills are conducted each calendar year at the CRN Site. These drills involve collecting and analyzing in-plant liquid and gaseous samples containing actual or simulated elevated levels, including use or simulated use of the post-emergency sampling system. The scenario is developed and the drills are conducted and critiqued by the site.
14.1.5 Radiological Dose Assessment Drills Radiological dose assessment drills are conducted at least twice each calendar year to test the procedures, calculation techniques, computer codes, and environmental assessment abilities of the CECC staff and support groups. These scenarios are developed and the drills are conducted and critiqued by EP.
14.1.6 Fire Drills Fire drills are conducted at the CRN Site in accordance with, and as required by, specific procedural requirements.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 14.1.7 Communication Drills Communications drills are conducted at least once each calendar year at the CRN Site.
14.2 EXERCISES Exercises are scheduled and conducted such that:
A biennial exercise will be conducted for the CRN Site to test the REP every 2 calendar years.
The CRN Site ensures that adequate emergency response capabilities are maintained during the interval between biennial exercises by conducting drills, including at least one drill involving a combination of some of the principal functional areas of the onsite emergency response capabilities. (The principal functional areas of emergency response include activities such as management and coordination of emergency response, emergency assessment, and plant system repair and corrective actions. During these drills supervised instruction is permitted, and activation of all of the emergency response facilities is not necessary. Sites have the opportunity to consider emergency management strategies, operating staff have the opportunity to resolve problems (success paths) rather than have controllers intervene, and the drills can focus on onsite training objectives. Sites shall enable the states and local authorities to participate in such drills when requested.)
TVA offers State and local authorities and support organizations the opportunity to participate in drills and exercises to the extent their assistance would be expected during an emergency at the CRN Site; however, participation is not required.
Major elements of the emergency plans and organizations are tested within an eight-year period.
The CRN Site initiates an exercise between 6:00 p.m. and 4:00 am at least once every eight years. The exact time of the exercise is unannounced.
14.3 SCENARIOS Drills and exercises are conducted in accordance with scenarios that have been properly planned, researched, and developed.
The drill and exercise scenarios include, but are not limited to, the following:
The basic objectives of each drill or exercise.
The date(s), time period, place(s), and participating organizations.
The simulated events.
A time schedule of real and simulated initiating events.
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A narrative summary describing the conduct of the exercises or drill, including simulated casualties, offsite fire department assistance, rescue of personnel, use of protective clothing, deployment of radiological monitoring teams, and public information activities.
Drill scenario development and implementation is the responsibility of the organization responsible for the specific drill.
Exercise scenario development and implementation is the responsibility of EP. Scenario specifics are not released by those representatives prior to the exercise.
Exercise scenarios will be developed to thoroughly test the REP on an eight year cycle. The exact time of an exercise is not released; however, a time span within which the exercise is to occur may be supplied to appropriate organizations and the news media so that the exercise is not confused with an actual emergency.
In the event a remedial exercise is required, a scenario is developed to demonstrate corrective measures have been taken regarding the described deficiencies.
14.4 CRITIQUES Representatives of Quality Assurance, INPO, NRC, DHS, State/local agencies and others may observe the exercise. Additional evaluators may be requested from other organizations as necessary. Evaluators are provided with sufficient material and a briefing prior to the exercise to become familiar with the Emergency Plan and exercise scenario.
At the conclusion of each exercise, a critique is conducted where the exercise and its participants are evaluated for effectiveness, procedural compliance and good practices. EP evaluates critique comments, develops a formal written report, coordinates corrective actions for deficiencies or items needing improvement, and follows up to ensure completion of corrective actions.
Drill critiques, critique reports, coordination of corrective action and follow-up to ensure completion is the responsibility of the organization administering the drill.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 15.0 TRAINING TVA ensures that personnel with specific duties and responsibilities in the NP-REP receive instruction in the performance of these duties and responsibilities.
15.1 ONSITE Site Nuclear Training/line organizations/site EP provide training in emergency procedures to permanent plant personnel and applicable non-plant personnel in accordance with plant training procedures.
For personnel with specific duties involving the NP-REP, this training consists of initial training classes and annual retraining to maintain familiarity with the features of the NP-REP.
Participation in drills, while not a requirement for all personnel with specific duties involving the NP-REP, does augment the training of those personnel who do participate. Key site responders are required to participate in drills on a periodic basis. The site EP group provides training to key site responders in the TSC and OSC, and the SED in accordance with applicable procedures.
Training for Plant Access is conducted in accordance with applicable CRN Site security procedures.
The Safety and Emergency Response Training Academy (SERTA) provides emergency medical care training to medical personnel and selected Nuclear Power personnel stationed at the CRN Site. Successful completion of training commensurate with their duties allows personnel to fulfill the role of medical care provider on the site MERT.
15.2 OFFSITE CECC personnel have current fitness for duty training. EP is responsible for ensuring that lesson plans are developed and training is conducted for CECC personnel. Training provided under this Plan is documented on an annual basis. Such documentation includes the date of the training, the names of those trained, and the training administered.
Training and annual retraining are provided to local plant support agencies (security, fire, ambulance, and hospital personnel) who may be involved with direct support of the site during an emergency.
Nuclear Support Services is responsible for providing agreement hospital and ambulance support training. The CRN Site is responsible for providing fire support training, with assistance from Nuclear Support Services, as needed. The CRN Site is responsible for providing local law enforcement (security) training. Training includes procedures for notification, basic radiation protection, expected roles, and site access procedures (as applicable).
15.3 PROFESSIONAL DEVELOPMENT TRAINING Full time EP staff members are afforded formal professional development training or activities commensurate with their duties and experience.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 16.0 PLAN MAINTENANCE 16.1 NP-REP Document Identification The CRN NP-REP has a controlled copy number.
Each page of the CRN NP-REP contains the following information:
NP-REP NP-REP Page 1 -or- Appendix A Rev. 1 Page A-1 Rev.1 Documents referenced in Appendix A, Attachment 1 are issued in accordance with appropriate State procedures.
Periodic Review The CRN NP-REP and the appendices are reviewed by CRN Site and EP staff annually for accuracy, completeness, operational readiness, and compliance with existing regulations and established policy. This review is initiated by EP and results are documented.
TVA has agreements with outside organizations for radiological emergency support to furnish specific services. Copies of the letters documenting these agreements are forwarded to EP and are reviewed annually and updated as necessary by EP.
Changes Revision to the CRN NP-REP may result from the reviews described in Subsection 16.1, drills, exercises, or changes in regulations. Changes are made and distributed according to Figure 16-
- 1. Changes identified from these reviews and drills and exercises are made as expeditiously as possible and are not necessarily held for submittal with an annual review.
Each line affected by a particular revision is marked in the margin. Changes in a revision are stated in the Revision Log; the pages affected and a brief explanation of the change are included in the Revision Log.
Plant Operations Review Committee (PORC) approval is obtained on CRN NP-REP revisions to Appendix A prior to their implementation. Changes to the main body of the CRN NP-REP and Appendices are scheduled for PORC review (up to 30 days based on the volume and complexity of the change). If comments cannot be resolved by the Director, Emergency Preparedness, and responsible site management, the comment is escalated to higher line management up to and including the TVA Chief Nuclear Officer. Changes to the CRN NP-REP are approved by the General Manager, Support Services, or designee.
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Distribution The CRN NP-REP, its additions, and revisions are authorized by an approval form and distributed by MS.
MS issues controlled revisions and ensures CRN NP-REP holders have received the changes by requiring that copy holders sign a receipt, which is provided, and return it within two weeks.
MS maintains a historical file of superseded REP material.
To provide REP holders with assurance that the Plan is up-to-date, cover pages and revision logs are distributed with each revision or addition. The revision log lists the latest revision number, the date revised, pages revised, and the reason for the revision.
16.2 EPIPs 16.2.1 Document Identification The CRN Site and CECC EPIP manuals bear a copy number. Pages of controlled documents are issued in accordance with approved procedures. Each page contains the following information similar to the following example:
CECC-EPIP-1 Page 5 of 12 Rev. 1 Each procedure in an EPIP manual has a cover page listing the revision number and the effective date. Each procedure also has a revision log or description of the revision. The procedure revision approval form is signed by the approving authority (or their designee) responsible for that EPIP as listed below:
EPIPs Approving Authority CECC Director, Emergency Preparedness CRN Plant Manager, CRN Site 54 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Draft Proposed Change to NP-REP or Appendix Plan Effectiveness Determination (PED)
(In Accordance With 10 CFR 50.54(q))
Site Review in Accordance With Approved Procedures (Sites Are Not Required To Review and Approve Other Sites Appendices)
EP Review/Coordination and Approval Vice President Support Services, or Representative No Significant Change As Yes Determined by PED?
NRC Review and Approval MS Issues Revision Figure 16-1 Update Procedure for NP-REP and Appendices 55 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 16.2.2 Periodic Review The EPIPs are reviewed annually for accuracy, completeness, operational readiness, and compliance with existing regulations by the responsible organization listed below. This review is initiated by Nuclear Support Services and results are documented.
EPIPs Organization CECC REP Staff CRN CRN Site EP coordinates a quarterly review of notification lists in the Radiological Emergency Notification Directory (REND). The review covers phone numbers and names and is documented by the REND Revision Log.
16.2.3 EPIP Changes CECC-EPIP Changes Revision to a CECC-EPIP may result from the reviews described in Section 16.2.2, drills and exercises, or changes to regulations. Changes are made and distributed according to Figure 16-
- 2. EPIPs receive a review in accordance with 10 CFR 50.54(q) screening process consistent with the REP.
Each line affected by a particular revision is marked. Changes in a revision are stated in the Revision Log; the pages affected and a brief explanation of the change are included in the Revision Log.
CRN-EPIP Changes Permanent, temporary, and emergency CRN-EPIP changes are issued as controlled documents to plant document holders in accordance with CRN Site document control practices. MS issues the changes to other document holders in accordance with MS document control practices.
CRN-EPIPs receive a review in accordance with 10 CFR 50.54(q) screening process consistent with the REP.
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Proposed Change Proposed Change to CECC-EPIP to Site-EPIP Review, Coordination, Review and and Approval
- Coordination
- Director, Emergency Preparedness Site Review and Approval According Review and Approval to Approved Procedures MS Issues CECC-EPIP MS Issues Revision to Onsite and Offsite Site-EPIP Revision Document Holders to Onsite Document Holders MS Issues Site-EPIP Revision to Offsite Document Holders
- EPIPs receive review in accordance with 10 CFR 50.54(q)
Screening process consistent with the REP.
Figure 16-2 Update Procedure for EPIPs 57 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 16.2.4 Distribution Each CECC-EPIP or revision is authorized by an approval form and distributed by MS. CRN-EPIP changes are distributed as discussed in Section 16.2.3.
Upon receiving revision from EP, those who are assigned controlled copies of an EPIP sign a receipt, which is provided, and return it within two weeks to MS.
Each revision is accompanied by a revised cover page for that procedure. MS maintains a historical file on superseded CECC-EPIP material and the site maintains a historical file on superseded CRN-EPIP material.
16.3 DOCUMENT RELATIONSHIPS The NP-REP and the associated supporting plans and procedures are issued as separate documents.
TVA maintains the following documents:
NP-REP.
CECC-EPIP.
CRN-EPIP.
REND.
On-shift Staffing Analysis Report (CRN Site).
These documents, along with the State Plan referenced in Appendix A, Attachment 1, may be issued separately or in combinations as applicable for the individual document holder.
16.4 AUDITS Quality Assurance conducts audits/reviews of the NP-REP program in accordance with 10 CFR 50.54(t) for compliance with existing regulations and its own internal requirements.
It is also responsible for offering recommendations on overall Plan improvement.
The results of the audit/review are documented, reported to appropriate organization management, and retained in the files for a period of five (5) years.
16.5 AGREEMENT LETTERS This Section includes a listing of agreements or contracts maintained for services of outside organizations during an emergency. The detailed agreements with the Tennessee Emergency Management Agency, the Department of Energy, Roane County, and the City of Oak Ridge will be addressed at COLA and documented in a Multi-Jurisdictional Emergency Response Plan.
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Agreement letters for offsite law enforcement support are maintained by CRN Site Nuclear Security Services and are updated annually. These agreement letters may be examined upon obtaining approval from the site Nuclear Security Services Manager.
Agreement letters with other offsite organizations are maintained by EP.
Agreements are maintained with ambulance services for 24-hour availability of EMT-staffed ambulances for the transport of irradiated/contaminated patients.
Agreements are maintained with fire departments having 24-hour assistance capabilities.
Agreements are maintained with DOE REAC/TS, Oak Ridge, Tennessee and the University of Tennessee Medical Center, Knoxville, Tennessee. Both medical facilities can provide 24-hour availability to TVA for medical/radiological emergencies which exceed in house capabilities.
INPO provides assistance in locating and arranging additional emergency manpower, equipment, and the services of various technical experts from industry sources. INPO maintains this utility data in the INPO Emergency Resources Manual.
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Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ) 17.0 DEFINITIONS AND ACRONYMS Activated - Minimum Activation Staff Positions are present onsite or in the facility within the assigned time following emergency declaration and ready to assume assigned functions.
Turnovers should be done as soon as practical, with consideration to performing them after the facility is activated.
Annual - Any 12 months, plus or minus 3 months with the following exceptions:
TVA executes annual activities associated with exercises, drills, emergency information for residents, media training, and offsite emergency response training are defined as "once per calendar year."
TVA annual training is for a 12-month period which includes a grace period extending to the end of the calendar quarter in which training is due.
ANI - American Nuclear Insurers.
CECC (Central Emergency Control Center) - The offsite TVA emergency response facility located in Chattanooga, Tennessee, with the overall TVA responsibility for response to an emergency. It consists of a director and staff to coordinate and direct TVAs efforts during the emergency.
CECC-EPIPs (Central Emergency Control Center Emergency Plan Implementing Procedures) -
The set of emergency response procedures developed to ensure that the capabilities described in Part 5A of the CRN Site ESPA are fulfilled in the CECC and offsite.
CEMP (Comprehensive Emergency Management Plan) - Beyond the Site Boundary, ad hoc actions following a release are addressed using a CEMP. Also referred to as an emergency operations plan (EOP), CEMP is addressed in the Federal Emergency Management Agencys (FEMA) Comprehensive Preparedness Guide (CPG) 101, Developing and Maintaining Emergency Operations Plans. CPG 101 is the foundation for State, territorial, Tribal, and local emergency planning in the United States. It promotes a common understanding of the fundamentals of risk-informed planning and decision making and helps planners at all levels of government in their efforts to develop and maintain viable, all-hazards, all-threats emergency plans. An EOP is flexible enough for use in all emergencies. It describes how people and property will be protected; details who is responsible for carrying out specific actions; identifies the personnel, equipment, facilities, supplies and other resources available; and outlines how actions will be coordinated. A CEMP is often referred to as a synonym for all hazards emergency planning.
COC - TVA Chattanooga Office Complex, Chattanooga, Tennessee.
CRN Site - The Clinch River Nuclear Site.
CRN-EPIPS (Clinch River Nuclear Site Emergency Plan Implementing Procedures) - The set of CRN Site emergency response procedures developed to ensure that the capabilities described in Part 5A of the CRN Site ESPA are fulfilled at the CRN Site.
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DHS - U.S. Department of Homeland Security.
DOE - U.S. Department of Energy.
DOT - U.S. Department of Transportation.
Drill - A supervised instruction period aimed at testing, developing, and maintaining skills in a particular operation. A drill is often a component of an exercise.
EAL (Emergency Action Level) - Specific events and criteria used to determine the appropriate emergency classification.
EDO - Emergency Duty Officer.
Emergency Classification (Also Class or Classification) - A scheme derived to categorize a plant emergency into one of four classes according to severity so that appropriate actions might be rapidly taken.
EMT (Emergency Medical Technician) - An individual certified under a recognized TVA system to provide emergency and related services to victims of illness or injury.
ENS (Emergency Notification System) - The phone line used to notify and inform the NRC of Event Status Data.
Environs - The atmospheric, terrestrial, and aquatic areas outside the site boundary.
EOC - Emergency Operations Center.
EP Staff - Emergency Services, Emergency Preparedness Staff.
EPA - U.S. Environmental Protection Agency.
Exclusion Area Boundary - The area for which TVA has absolute authority for exclusion of personnel and property within the Site Boundary. This boundary is used in SSAR dose assessments to define the distance to the first member of the public and is defined in the SSAR.
Exercise - An event that tests the integrated capability and a major portion of the basic elements existing within the Emergency Plan.
FEMA (Federal Emergency Management Agency) - An agency of the federal government.
Hostile Action - An act toward a nuclear site or its personnel that includes the use of violent force to destroy equipment, takes hostages, and/or intimidates the licensee to achieve an end.
This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included. Hostile Action should NOT be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the nuclear site.
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Hostile Force - One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
HPN (Health Physics Network) - The NRCs health physics information line.
IC - (Initiating Condition) - An event or condition that aligns with the definition of one of the four emergency classification levels by virtue of the potential or actual effects or consequences.
INPO - Institute for Nuclear Power Operations.
JIC (Joint Information Center) - A center established near the CRN Site to assist the news media in providing press coverage during an emergency.
LRC (Local Recovery Center) - A facility located near the CRN Site used as additional office space, if necessary, for TVA personnel during recovery operations. The facility is also available for NRC use during an emergency. Additionally, the LRC may serve as an alternate emergency response facility if needed, and can also serve as a staging area for individuals or teams prior to dispatch to the CRN Site.
MASP - Minimum Active Staffing Positions.
MERT - Medical Emergency Response Team.
Missiles - As used in the EALs, a missile is any hurled object (e.g., debris from explosions, fragments from rotating equipment breaks).
Monthly - Any 30-day period, plus or minus 7 days.
MS - Management Services.
NOAA - National Oceanic and Atmospheric Administration.
NOUE - Notification of Unusual Event.
NP - Nuclear Power.
NP-REP (Nuclear Power Radiological Emergency Plan) - The Plan which provides the policies and the actions to be used to minimize the impact on personnel, public, and the environment from an emergency at a TVA nuclear plant.
NRC - U.S. Nuclear Regulatory Commission.
NRF - National Response Framework.
NSS - Nuclear Security Services.
NSSS - Nuclear Steam Supply System.
Offsite - The area around a nuclear plant site that is not onsite.
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Onsite - Onsite is defined according to the subject ... (1) in relation to SSAR dose assessment, onsite is "within the exclusion area;" (2) in relation to accountability and site notifications, onsite is "within the site's outermost secured area;" (3) in relation to EP dose assessments onsite is defined as "1000 meter radius;" and (4) in other contexts onsite is "within the reservation boundary."
ODS (Operations Duty Specialist) - The 24-hour per day emergency contact for TVA.
ORAU (Oak Ridge Associated Universities) - A nonprofit corporation and prime contractor with DOE for operation of the REAC/TS facility.
ORMMC (Oak Ridge Methodist Medical Center) - In conjunction with the REAC/TS facility, provides continuing medical care to radiological emergency victims.
OSC (Operations Support Center) - An area set aside within the plant for providing an assembly area for operational support personnel during an emergency situation.
PABX (Private Automatic Branch Exchange) - A communications system, controlled by TVA, employing microwave and land line transmissions.
Plant Manager - Key plant management serving as the Shift Manager's supervisory contact during off-hours.
PORC (Plant Operations Review Committee) - A group of plant supervisors whose function is to provide a safety review of procedures and operations for the plant and make recommendations to the Plant Manager on these matters.
Quarterly - Any three-month period, plus or minus one month.
RAA - Radiological Assessment Area of CECC.
Rad Protection - Radiological Protection.
R or r - For purposes of this Plan and its implementing procedures, radiation exposure as expressed in units of R/hr and subunits, thereof, is equivalent to dose (rad) and dose equivalent (rem).
RCI - Radiological Control Instructions.
REAC/TS (Radiation Emergency Assistance Center/Training Site) - A special facility that is operated by ORAU for DOE, to provide a sophisticated facility to handle radiological emergency victims. The REAC/TS facility is located in ORMMC.
Recovery - The post emergency activities in which the plant conditions are assessed and the plant is returned to an operational mode.
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REND (Radiological Emergency Notification Directory) - A directory of key personnel for support of the CECC.
REP - Radiological Emergency Plan.
RMCC (Radiological Monitoring Control Center) - An environmental monitoring coordination center.
SAE - Site Area Emergency.
Security Condition- Any Security Event as listed in the approved Security Contingency Plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A Security Condition does NOT involve a Hostile Action.
SED - Site Emergency Director.
Semiannual - Any six-month period, plus or minus 45 days. (The exception to this is for drills for which it is defined as "twice each calendar year.")
SEOC- State Emergency Operations Center.
Site Boundary - The appropriate boundary between "onsite" and "offsite."
SSAR (Site Safety Analysis Report) - The report required by 10 CFR 52.17(a)(1) to be included in each application for an early site permit. The SSAR includes a description of the facility, the maximum levels of thermal and radiological effluents, and a description of seismic, meteorological, hydrologic, and geologic characteristics of the proposed site.
SM - Shift Manager.
TEDE - Total Effective Dose Equivalent as defined by 10 CFR 20.1201.
TSC (Technical Support Center) - An assembly/work area for designated support individuals knowledgeable of and responsible for engineering and management support of reactor operations in the event of an emergency.
UE (Unusual Event) - terminology that is commonly used referring to the term Notification of Unusual Event (NOUE). UE and NOUE are synonymous.
WARL (Western Area Radiological Laboratory) - TVA laboratory located in Muscle Shoals, Alabama, capable of analyzing environmental samples for radioactive content.
Weekly - Any seven-day period, plus or minus two days.
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Attachment 1 Justification for the Central Emergency Control Center Under 10 CFR Part 50, Appendix E, Section IV.E.8, TVA is required to provide a licensee near-site Emergency Operations Facility (EOF) from which effective direction can be given and effective control can be exercised during an emergency. The NRC provides guidance for design and location of the EOF in NUREG-0696, Functional Criteria for Emergency Response Facilities (NUREG-0696). Since the early 1980s, TVA has used a centralized concept for providing the EOF function for its nuclear sites. Consistent with this approach, the CRN Site Emergency Plan relies on the use of the Central Emergency Control Center (CECC) as the EOF for the CRN Site. The CECC serves as the EOF for the other TVA nuclear plants (Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN)). The CECC is located in the TVA Chattanooga Office Complex (COC) in Chattanooga, Tennessee, approximately 78 air miles from the CRN Site. The CECC is further than 20 miles from the CRN Site Technical Support Center (TSC), as is the case for BFN, SQN, and WBN, but does not alter the functions of the EOF as described in NUREG-0696.
The use of the CECC as the EOF for the CRN Site allows TVA to continue to operate a standardized program for corporate management and response to radiological emergencies at TVA nuclear facilities. The effectiveness of CECC operations has been demonstrated during numerous drills and exercises. Communications systems, data links, and staffing have been incorporated and tested. Using the CECC for the CRN Site also allows TVA to apply its corporate emergency response structure and experience to the CRN Site Emergency Plan.
TVA has discussed this concept with the Tennessee Emergency Management Agency (TEMA).
TEMA is familiar with the CECC because the facility is used for responding to radiological emergencies at SQN and WBN. Through the letter referenced in SSAR, Section 13.3 of the CRN ESPA, TEMA confirms their support of the TVA emergency response program, included the use of the CECC in Chattanooga.
Access to the station by the NRC site team is accommodated. The CRN Site has a Local Recovery Center (LRC) which is a pre-designated facility dedicated for use by offsite TVA and NRC personnel that may be assigned to the CRN Site for recovery operations. In addition, the LRC may be used by the NRC during the event as an area near the site for assessment and assistance and has the capability to communicate offsite. Additional information regarding the LRC can be found in section 8.1.3 of this Plan and in A.4.8 in Appendix A.
The CECC includes space for State liaisons reporting to the CECC in Chattanooga.
The following discussion provides an evaluation of the CECC against the criteria provided in NUREG-0696.
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Evaluation Against NUREG-0696:
The CECC is designed to provide for the effective and timely performance of the following functions:
Management of overall licensee emergency response.
Coordination of radiological and environmental assessment.
The primary role of the CECC is to relieve the plant staff of the functions of keeping the federal, State, and county emergency response organizations informed, for directing dose assessment and field monitoring, for managing the informational needs of the media, interested industry groups, and elected officials, and for supporting the emergency assessment needs of the TSC staff. The NRC will have access to plant data through the CECC computer system and the Emergency Response Data System (ERDS). The NRC also has telephones on the Emergency Telecommunications System (ETS) in Chattanooga.
Equipment exists in the CECC for the acquisition, display, and evaluation of radiological, meteorological, and plant system data. Because a similar set of data currently used for BFN, SQN, and WBN are required for the CRN Site, the plant and effluent data would be provided on as timely a basis at the CECC as it would be at a near-site location.
Normal industrial security is already provided for the CECC and processes are already established to upgrade the security of the facility during an activation.
Location, Structure, and Habitability The CECC is located in the northeast corner of the sixth floor of Lookout Place in the TVA COC in Chattanooga, Tennessee. The CECC has proven to be an effective facility for implementation of the TVA nuclear station emergency plans. The CECC is used for existing TVA nuclear plants at the BFN, SQN, and WBN sites. The facility is more than ten miles from any of the TVA nuclear stations; therefore, there are no specific habitability criteria.
Staffing and Training Incorporation of CRN emergency response functions into the CECC will not adversely affect the ability of TVA to staff the CECC in a timely manner. The CECC is staffed with experienced personnel from the TVA COC and personnel from one or more TVA nuclear plants. The CECC staff has demonstrated their ability to staff the CECC within required time-frames following emergency declaration during previous staff augmentation drills. The CECC staff includes personnel to manage overall licensee emergency response, and coordinate radiological and environmental assessment.
Size The CECC size has proven to be adequate during drills and exercises for the existing TVA nuclear facilities. In addition, the NRC has workspace co-located with the decision makers, radiological assessment, and emergency assessment personnel.
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Radiological Monitoring The CECC is beyond 10 miles from any nuclear stations, and therefore does not require radiological monitoring equipment.
Communications The communications systems available in the CECC consist of:
Central Office Trunks.
Tie-lines.
Digital Services.
Privately-owned/maintained microwave systems.
Privately-owned fiber-optic systems.
NRC ETS phones.
EP Radio System.
The emergency communications systems at the CECC are designed to provide a reliable, timely flow of information between the parties having an emergency response role. The single facility results in commonality of communications and interface with offsite officials and liaisons. The EP telephone system continues to be the primary means of communicating changes in event classification. This system operates on a combination of the TVA telecommunications network and leased circuits.
The offsite communications network is used to communicate with federal, State, and other supporting agencies. Access to these agencies is provided through several redundant, diverse routes. This diversity provides offsite routing through more than one type of facility. These facilities include, but are not limited to, commercial facilities such as central office trunks, tie-lines and digital services, plus privately owned and maintained microwave and fiber-optic systems. The offsite telecommunications network is designed to facilitate traffic in the most fail-safe manner to the emergency response organizations.
The Emergency Notification System (ENS) and Health Physics Network (HPN) (NRC FTS 2000 System) communication systems provide communications from each site TSC, Control Room, and the CECC to the NRC Headquarters and regional offices. These telephones are tested on a periodic basis consistent with the CRN Site Emergency Plan.
The EP radio system is a VHF mobile radio system which provides redundant radio coverage of the Plume Exposure Pathway (PEP) Emergency Planning Zone (EPZ) and provides radiological monitoring vehicles with mobile communications to other vehicle(s) and to the following locations: Radiological Control, TSC, Control Room at each TVA plant, and the CECC.
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Instrumentation, Data System Equipment, and Power Supplies Various plant parameters are available to the CECC staff via a connection through the TVA CECC computer network. Data available at the CECC provides a snapshot of data from each units integrated set of plant data. Plant data can be displayed at the CECC. These data are sufficient to perform emergency assessment and evaluate the potential environmental consequences of an emergency at the CRN Site. Detailed discussion on CRN Site plant-specific parameters are described in the Emergency Plan. The computers in the dose assessment area are capable of running the dose projection computer programs and accessing plant status data.
Hourly and 15-minute average meteorological data from the plant Environmental Data Station are available to the CECC, TSC, State, and LRC. The CECC computer system provides access to up to the most recent 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of this data. A meteorologist in the CECC provides meteorological information to the CECC staff in support of offsite dose projections.
The CECC draws its primary power from commercial power. A loss of commercial power should not impact any of the voice or data communications equipment located in the CECC. Common TVA telecommunications infrastructure that supports CECC functions, including, but not limited to fiber optic transmission equipment, telephone switching equipment, and data network routers, is configured to operate from at least one and usually multiple backup power sources in the event of a loss of commercial power. These backup sources include generator, dc battery and uninterruptible power supply systems.
Technical Data and Data Systems As discussed in the previous section, a variety of plant parameters are provided over the TVA communications network to the CECC.
Reports Availability and Management Hard copies of key reference materials are maintained in the CECC. In addition, station design documentation, plant drawings, procedures, etc. are available via Local Area Network connection from the Business Support Library.
The following information is available for the CRN Site at the CECC:
Plant technical specifications.
Plant operating procedures.
Emergency operating procedures.
Final Safety Analysis Report.
Up-to-date licensee, State, and local emergency response plans.
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Conclusion The CECC meets the functional and design criteria provided in NUREG-0696 for an EOF with the exception that it is located more than 20 miles from the CRN Site. This document describes the TVA approach to assuring that these functional and design criteria are met and maintained.
The consolidation of TVA corporate emergency response functions into a centralized facility provides a timely and effective response to a radiological emergency at the CRN Site.
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Appendix A Table of Contents A.1 CLINCH RIVER NUCLEAR SITE AND EMERGENCY PLANNING ZONE DESCRIPTION........................................................................................................... 1 A.1.1 FACILITY AND SITE CHARACTERISTICS ................................................... 1 A.1.1.1 Nuclear Power Facility .................................................................................. 1 A.1.1.2 Site Location and Description ...................................................................... 1 A.1.2 EMERGENCY PLANNING ZONES ................................................................ 1 A.2 EMERGENCY ACTION LEVELS ............................................................................ 3 A.3 SITE EMERGENCY ORGANIZATION (CONCEPT OF OPERATIONS) ........... 4 A.3.1 OPERATIONS ................................................................................................. 4 A.3.2 FIRE PROTECTION ........................................................................................ 4 A.3.3 RADIATION PROTECTION (RP) / CHEMISTRY ........................................... 4 A.3.4 SECURITY ...................................................................................................... 4 A.3.5 MAINTENANCE .............................................................................................. 4 A.3.6 ONSITE EMERGENCY MANAGEMENT ORGANIZATION ........................... 4 A.3.6.1 Site Vice President ........................................................................................ 5 A.3.6.2 Site Emergency Director ............................................................................... 5 A.3.6.3 Operations Manager ...................................................................................... 5 A.3.6.4 Technical Assessment Manager .................................................................. 6 A.3.6.5 Nuclear Security Manager ............................................................................ 6 A.3.6.6 Radiological Protection Manager ................................................................. 6 A.3.6.7 Chemistry Manager ....................................................................................... 7 A.3.6.8 OSC Manager ................................................................................................. 7 A.3.6.9 OSC Rad Protection Representative ........................................................... 7 A.3.6.10 Other OSC Representatives ......................................................................... 8 A.4 EMERGENCY RESPONSE FACILITIES, EQUIPMENT, AND SUPPLIES... 11 A.4.1 TECHNICAL SUPPORT CENTER ................................................................ 11 A.4.2 OPERATIONS SUPPORT CENTER ............................................................. 13 A.4.3 LABORATORY AND EQUIPMENT .............................................................. 13 A.4.4 ONSITE MONITORING SYSTEMS AND EQUIPMENT ............................... 13 A.4.4.1 Natural Phenomena ..................................................................................... 13 A.4.4.2 Radiological Monitors ................................................................................. 14 A-ii Revision 1
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Appendix A A.4.4.3 Process Monitors (Non-radiological) ......................................................... 14 A.4.4.4 Safety Parameter Display System (or equivalent) .................................... 14 A.4.4.5 Emergency Response Data System .......................................................... 14 A.4.4.6 Fire Protection ............................................................................................. 15 A.4.4.7 Environment................................................................................................. 15 A.4.5 EMERGENCY EQUIPMENT ......................................................................... 16 A.4.5.1 Emergency Communications Equipment ................................................. 16 A.4.5.2 First Aid and Medical Facilities .................................................................. 16 A.4.6 ADDITIONAL LOCAL SUPPORT ................................................................. 17 A.4.6.1 Fire ................................................................................................................ 17 A.4.6.2 Law Enforcement......................................................................................... 17 A.4.6.3 Vendor Support ........................................................................................... 17 A.4.7 ASSEMBLY/ACCOUNTABILITY ALARM .................................................... 17 A.4.8 LOCAL RECOVERY CENTER ..................................................................... 17 A.5 MAINTAINING EMERGENCY PREPAREDNESS ............................................ 18 A.5.1 RESPONSIBILITY FOR THE EMERGENCY PREPAREDNESS EFFORT.. 18 A.5.2 PROCEDURES ............................................................................................. 18 A.5.3 INDEPENDENT REVIEWS OF EMERGENCY PREPAREDNESS .............. 18 A.6 ALERT AND NOTIFICATION SYSTEM (NOT APPLICABLE) ....................... 19 A.7 TRAINING AND DRILLS .............................................................................. 19 A.7.1 TRAINING PERSONNEL .............................................................................. 20 A.7.2 DRILLS AND EXERCISES ........................................................................... 20 A.8 EMERGENCY PLAN IMPLEMENTING PROCEDURES ................................. 21 STATE MULTIJURISDICTIONAL RADIOLOGICAL EMERGENCY RESPONSE PLAN .................................................................................................. 22 EMERGENCY EQUIPMENT AND SUPPLIES ................................................... 23 CROSS REFERENCE TO REGULATIONS AND GUIDANCE ....................... 24 A-iii Revision 1
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Appendix A A.1 CLINCH RIVER NUCLEAR SITE AND EMERGENCY PLANNING ZONE DESCRIPTION A.1.1 FACILITY AND SITE CHARACTERISTICS A.1.1.1 Nuclear Power Facility The Clinch River Nuclear (CRN) Site is located on the Clinch River Property and is used as the location to construct and operate Small Modular Reactors (SMRs).
A.1.1.2 Site Location and Description The CRN Site Property covers an area of approximately 1,200 acres located adjacent to the Clinch River in Roane County, Tennessee. The CRN Site lies north of U.S. Interstate 40, approximately midway between the communities of Harriman and Farragut in the eastern portion of Tennessee.
Site Safety Analysis Report (SSAR) Chapter 2 provides additional information regarding the physical characteristics of the proposed site, including the preliminary site layout and potential hazards in the site vicinity. The Environmental Report provides detailed information addressing land use and other features of the proposed site and surrounding area.
A.1.2 EMERGENCY PLANNING ZONES Section 50.47(c)(2) of 10 CFR 50 establishes two Emergency Planning Zones (EPZs) for consideration in nuclear power plant emergency planning. For the CRN Site, the plume exposure pathway (PEP) EPZ encompasses the same area as the CRN site boundary. The ingestion exposure pathway EPZ encompasses an area that is yet to be determined. TVA intends to address this in the CRN Site Combined License Application (COLA). Of particular interest regarding the CRN Site is the overlapping emergency planning zone for the U.S.
Department of Energy (DOE) Oak Ridge Reservation.
Figure A.1-1 provides a map of the CRN Site.
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Appendix A Figure A.1-1 CRN Site Boundary Emergency Planning Zone A-2 Revision 1
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Appendix A A.2 EMERGENCY ACTION LEVELS Part 5A Section 4.2 indicates that, recognition of the emergency class is primarily a judgment matter for plant personnel. The initiating conditions (ICs) used for recognizing and declaring the emergency class are based on specific measurable values or observable conditions defined as Emergency Action Levels (EALs). These can be combinations of specific instrument readings (including their rates of change), annunciator warnings, and time periods during which certain conditions exist, etc. CRN Site Emergency Plan Implementing Procedures (CRN-EPIPs) provide details regarding instrument readings and parameters required for determination of these EALs.
Tennessee Valley Authority (TVA) uses these EALs as thresholds for determining the emergency classifications. TVA develops the EALs based on industry guidance, engineering assessments, and insights provided by the reactor plant supplier.
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Appendix A A.3 SITE EMERGENCY ORGANIZATION (CONCEPT OF OPERATIONS)
TVA maintains an organization capable of responding to a radiological emergency. The on-shift staff is continually present on a 24-hour basis. TVA will specify on-shift staffing at COLA. The on-shift staffing would be evaluated pursuant to Section IV.A.9 of Appendix E of 10 CFR 50.
A.3.1 OPERATIONS The minimum staff required to conduct routine and immediate emergency operations is maintained at the station consistent with 10 CFR 50.54(m) and the facility Technical Specifications. Staffing is described in SSAR Section 13.1. Site procedures provide the details of the normal site organization, including reporting relationships.
A.3.2 FIRE PROTECTION The Fire Shift Operations is staffed by qualified personnel that meet the requirements established in the CRN Site Fire Protection Plan.
A.3.3 RADIATION PROTECTION (RP) / CHEMISTRY The RP/Chemistry is staffed by qualified personnel that meet the requirements established in the CRN Site Technical Specifications.
A.3.4 SECURITY Security is staffed by qualified personnel that meet the requirements established in the CRN Site Physical Security Plan.
A.3.5 MAINTENANCE Maintenance is staffed by personnel who are available to respond to postulated events that could involve one or more of the three commonly recognized technical disciplines; mechanical, electrical, or instrumentation. Each maintenance team member has a background in one or more discipline(s). Team members may perform cross-disciplinary work if they have a background to perform the respective task/activity. The Maintenance team members provide a first response capability within the bounds of the actions required during the initial phase of a radiological emergency.
A.3.6 ONSITE EMERGENCY MANAGEMENT ORGANIZATION CRN-EPIPs describe the duties and responsibilities of the Onsite Emergency Management Organization positions. Figure A.3-1 illustrates the organization for the Technical Support Center (TSC), including those positions that must respond within a prescribed period of time following an Alert or higher emergency declaration. The prescribed period of time for responding to the TSC will be addressed in the CRN Site COLA. Figure A.3-2 illustrates the organization for the Operations Support Center (OSC).
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Appendix A A.3.6.1 Site Vice President:
The Site Vice President:
- Serves as a corporate interface for the Site Emergency Director (SED), relieving them from duties which could distract from the SED primary purpose of plant operations and emergency mitigation activities.
- Provides assistance to the SED by providing TVA policy direction; directing site resources to support the SED in emergency mitigation activities; and providing a direct interface on overall site response activities with the U.S. Nuclear Regulatory Commission (NRC), the U.S. Department of Homeland Security (DHS), or other federal organizations responding to the site, Central Emergency Control Center (CECC)
Director, or onsite media.
- At their discretion, may provide an interface at the appropriate offsite location on the overall site response activities with State and local agencies, NRC region/headquarters, or Joint Information Center (JIC).
- Provides support to other emergency operation centers as necessary.
A.3.6.2 Site Emergency Director The Site Emergency Director (SED) is located in the TSC and:
- Directs onsite emergency mitigation activities.
- Consults with the CECC Director, and Senior Site Executive on significant events and their related impacts.
- Identifies onsite protective actions.
- Apprises the NRC with regard to emergency mitigation actions being taken.
- Makes final decision on personnel entrance to radiologically-hazardous areas when Radiological (Rad) Protection recommends against the entry.
- Initiates long-term 24-hour per day emergency mitigation operations.
- Determines the emergency classification.
The SED or Control Room staff is responsible for making initial notifications to the appropriate State organization. The SED is also responsible for emergency dose authorizations for personnel under their direction and control (these responsibilities cannot be delegated).
A.3.6.3 Operations Manager The Operations Manager is located in the TSC and:
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- Directs operational activities.
- Keeps the SED informed on plant status and operational problems.
- Performs damage assessment as necessary.
- Assures the Control Room is aware of the emergency assessment and response.
- Recommends solutions and mitigating action for operational problems.
A.3.6.4 Technical Assessment Manager The Technical Assessment Manager is located in the TSC and:
- Provides information, evaluations, and projections to the SED.
- Coordinates assessment activities with the CECC.
- Keeps the Technical Assessment Team informed of plant status.
- Assesses effluents.
- Directs the Technical Assessment Team.
- Projects future plant status based on present conditions.
The Technical Assessment Manager provides pertinent information to appropriate organizations via a continuously used and monitored telephone communications hookup.
A.3.6.5 Nuclear Security Manager The Nuclear Security Manager is located in the TSC and:
- Directs activities of Nuclear Security Services personnel.
- Controls access to site and Control Rooms.
- Reports on site accountability/evacuation as defined in CRN-EPIPs.
A.3.6.6 Radiological Protection Manager The Radiological (Rad) Protection Manager is located in the TSC and:
- Assesses in-plant and onsite radiological conditions.
- Directs onsite Rad Protection activities.
- Coordinates additional Rad Protection support with the CECC.
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- Recommends protective actions for onsite personnel to the SED.
- Maintains radiological conditions status information.
- Coordinates assessment of radiological conditions with the CECC.
- Maintains the in-plant radiological status boards.
- Assists the Maintenance Superintendent in briefing maintenance teams.
- Assigns appropriate Rad Protection support to maintenance teams.
- Makes final recommendation to the SED for personnel entry to radiologically hazardous environments.
A.3.6.7 Chemistry Manager The Chemistry Manager is not a minimum required staff position. When this position is staffed, the Chemistry Manager is located in the TSC and:
- Coordinates assessment of effluents with the CECC.
- Coordinates post-emergency sampling activities.
- Directs radiochemical lab activities.
- Assesses effects on radwaste and effluent treatment systems.
A.3.6.8 OSC Manager The OSC Manager is located in the Operations Support Center and:
- Directs repairs and corrective actions in coordination with the TSC.
- Performs damage assessment.
- Directs activities of OSC.
- Coordinates maintenance teams and ensures they have received proper briefings and are accompanied by a Rad Protection Technician, as necessary.
A.3.6.9 OSC Rad Protection Representative The OSC Rad Protection Representative is located in the TSC and:
- Directs activities of the Rad Protection lab.
- Ensures Rad Protection coverage of damage repair teams.
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A.3.6.10 Other OSC Representatives Other OSC representatives are located in the OSC and provide support to the OSC Manager within their respective technical disciplines. Responsibilities include:
- Providing and supervising personnel and other resources within their respective disciplines.
- Providing pre-job and post-job briefings to personnel.
- Communicating technical information to personnel located in the TSC.
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Appendix A Site Site Vice Emergency President Director Administrative Technical Support Advisor(s)
(as needed) (as needed)
Technical Radiation Operations Maintenance Assessment Protection Manager Manager Manager Manager Technical Support Support Support Assessment Staff Staff Staff Team Chemistry Manager Figure A.3-1 Technical Support Center Organization A-9 Revision 1
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Appendix A Operations Support Center Manager Administrative Support Security (as needed)
Safety Fire Protection (as needed)
Radiation Chemistry Operations Maintenance Protection Representative Representative Representative Representative Radiation Chemistry Operations Maintenance Protection Staff Staff Staff Staff Figure A.3-2 Operations Support Center Organization A-10 Revision 1
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Appendix A A.4 EMERGENCY RESPONSE FACILITIES, EQUIPMENT, AND SUPPLIES Specific plant areas, onsite and offsite facilities, and equipment are selected and provided for use during a radiological emergency at the CRN Site. The preselection, allocation, and inclusion of emergency facilities assure that needed services and equipment are available for use during emergency conditions.
A.4.1 TECHNICAL SUPPORT CENTER The CRN Site is equipped with a Technical Support Center (TSC). The TSC is part of the emergency response facilities provided for emergency response to accidents. The TSC is established consistent with NUREG 0696, Functional Criteria for Emergency Response Facilities (NUREG-0696), as described below.
Function The TSC provides plant management and technical support personnel (including the appropriate number of NRC personnel) with a facility from which they can assist plant operating personnel located in the Control Room during an emergency. The SED and the NRC representative are located in the same general area to promote proper communications.
Location The TSC has the ability to retrieve plant data and displays available in the Control Room and is equipped with sophisticated communications systems. This precludes the need for frequent face to face interchange between the TSC and Control Room personnel.
Staffing and Training The level of staffing and training is described in the Emergency Plan. The TSC accommodates the required personnel to support an emergency affecting the CRN Site. The level of staffing may vary according to the severity of the emergency condition.
Size The TSC provides working space, without crowding, for the personnel assigned to the TSC at the maximum level of occupancy. The working space is sized for a minimum of 25 persons.
Minimum size of working space is approximately 75 ft2 per person.
Structure The TSC is designed in accordance with the Uniform Building Code (UBC) to withstand earthquakes and high winds.
Habitability The ventilation system is operated in accordance with approved procedures and is manually controlled from the TSC. In addition, portable radiation monitors are available to personnel in the TSC. Equipment and supplies are provided in accordance with the Emergency Plan. The A-11 Revision 1
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Appendix A ventilation system includes high efficiency particulate air (HEPA) filters and charcoal filters. The ventilation system is designed to maintain exposures at or below (5 rem total effective dose equivalent (TEDE) as defined in 10 CFR 50.2 for the duration of an emergency. The TSC structure, shielding, and ventilation system are designed to protect the TSC personnel from radiological hazards.
Communications The TSC has reliable voice communications to the Control Room, the OSC, the CECC, and the NRC. Provisions for communications with State and local operations centers are also provided in the TSC. The communications facilities include the means for reliable primary and backup communication.
Instrumentation, Data System Equipment, and Power Supplies The TSC is provided with reliable power and backup power supplies. Lighting is powered by the normal and backup electrical supply system. An emergency battery operated lighting system is installed. Power for vital information systems is provided by reliable power supplies including a battery backed Uninterruptible Power Supply (UPS) system.
Technical Data and Data System Within the TSC, technical and operational data and information is available for each unit.
Support facilities are located within the TSC to support long term operation of the TSC. The TSC is equipped with a computer system which provides source term and meteorological data and technical data displays to allow TSC personnel to perform detailed analysis and diagnosis of abnormal plant conditions, including assessment of any significant release of radioactivity to the environment. Human Factors Engineering (HFE) is incorporated into the design of the TSC related to the display and availability of plant data.
Records Availability and Management The TSC has ready access to plant records. The documents maintained in the TSC include:
- Technical Specifications.
- Plant Operating Procedures.
- Emergency Operating Procedures.
- Final Safety Analysis Reports.
- System piping and ventilation diagrams and heating, ventilation, and air conditioning (HVAC) flow diagrams.
- Piping area diagrams.
- Records needed to perform the functions of the CECC when it is not operational.
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Appendix A In addition, copies of the above-listed documents and the following documents are available in CRN Site Document Control:
- Plant operating records.
- Plant Review Board records and reports.
The above records are updated as necessary to maintain currency and completeness.
Operations at this facility are directed by the SED when the TSC is operational.
CRN-EPIPs describe the staffing and operation of the TSC.
A.4.2 OPERATIONS SUPPORT CENTER The site is equipped with an OSC. The OSC provides a centralized area and the necessary supporting resources for the assembly of designated operations support personnel during emergency conditions. The OSC provides the resources for communicating with the Control Room and the TSC. This permits personnel reporting to the OSC to be assigned to duties in support of emergency operations.
Designated plant support personnel assemble in the OSC to provide support to both the Control Room and TSC. The primary function of the OSC staff is to dispatch assessment, corrective action, and rescue personnel to locations in the plant, as directed by the TSC and Control Room. TVA provides for an OSC assembly area separate from the Control Room and the TSC.
Personnel reporting to the OSC can be assigned duties in support of emergency operations.
The OSC is not designed to remain habitable under all projected emergency conditions; however, implementing procedures make provisions for relocating the OSC as needed, based on ongoing assessments of plant conditions and facility habitability. The SED directs relocation of the OSC, if required.
CRN-EPIPs describe the staffing and operation of the OSC.
A.4.3 LABORATORY AND EQUIPMENT TVA provides laboratory facilities adequate for chemical and radiological analyses of relevant sample media, including solid, liquid, and air samples. The laboratory equipment provides capabilities to perform isotopic analyses of samples to identify radionuclides present in the samples and their concentrations per unit mass or volume, as appropriate.
A.4.4 ONSITE MONITORING SYSTEMS AND EQUIPMENT Information regarding onsite monitoring systems and equipment is addressed in the COLA.
A.4.4.1 Natural Phenomena In the event an emergency is the result of a natural phenomenon, there is instrumentation to monitor its severity. The Environmental Data Station is located onsite and contains instruments capable of measuring wind direction, wind speed, and temperatures. Seismic instrumentation is A-13 Revision 1
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Appendix A available in the plant to monitor acceleration levels of ground movement. Hydrological monitoring systems are installed to supply flow and level information. Meteorological and seismic instrumentation have readily accessible readout in the Control Room.
In the event of a failure of the onsite natural phenomena monitoring systems, TVA maintains access to back-up data sources. These back-up sources include telephone and web-based contact with federal government data sources and alternative sources, including university and news media sources.
A.4.4.2 Radiological Monitors The installed Radiation Monitoring System consists of process monitors and area monitors.
Additional information regarding this system is addressed in the CRN Site COLA.
A.4.4.2.1 Process Monitors (Radiological)
The process system continuously monitors selected lines containing or possibly containing radioactive effluents. The system's function is to warn personnel of increasing radiation levels, to give early warning of a system malfunction, and to record and control discharges of radioactive liquids and gases to the environment.
A.4.4.2.2 Area Radiation Monitors Area monitors are placed at specific locations in the plant.
A.4.4.2.3 Portable Monitors Portable radiation detection equipment consists of low-range and high-range instruments to measure gamma dose rates. Instruments for alpha, beta-gamma, and neutron radiation measurements are available. Sampling equipment is available to collect and analyze air samples. The Counting Room has appropriate equipment for isotopic analysis of sample media.
A.4.4.3 Process Monitors (Non-radiological)
The Control Room provides a central, protected location for placement of the necessary instrumentation to assess plant systems status, including reactor coolant system pressure and temperature, containment pressure and temperature, liquid levels, flow rates, fire detection equipment, and meteorological instrumentation.
A.4.4.4 Safety Parameter Display System (or equivalent)
The plant is equipped with the capability to display information required for a Safety Parameter Display System (SPDS) or an equivalent system.
A.4.4.5 Emergency Response Data System The Operations Duty Specialist (ODS) activates the Emergency Response Data System (ERDS), which transmits selected plant monitoring data to the NRC, within one hour of the declaration of an Alert or higher level emergency classification.
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Appendix A A.4.4.6 Fire Protection The plant's fire protection system provides extinguishing agents with the capability of extinguishing any single or probable combination of simultaneous fires that might occur. TVA controls the use of combustible materials.
A.4.4.7 Environment Facilities available for assessing the impact of plant operations on the environment include atmospheric monitoring stations, direct gamma radiation detectors, and water sampling capabilities. TVA maintains this equipment for use in the routine environmental radiological monitoring program and the equipment is available for use in the event of a radiological emergency condition.
The atmospheric monitoring network is divided into three subgroups. Local air monitors are located at or adjacent to the CRN Site Boundary in the directions of predominant wind flow.
Perimeter monitors are located farther from the plant in areas of relatively high population densities and/or in the direction of predominant air flow. Remote monitors (controls) are located at greater distances from the site.
Primary dosimeters are placed at selected sites around the plant. These dosimeters are located typically in each of the meteorological sectors at or near the CRN Site Boundary and at greater distances.
In addition to these facilities, established sampling points for milk, vegetation, soil, fish, and sediment are located in the vicinity of the plant. TVA may collect samples from these stations on a non-routine basis as needed.
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Appendix A A.4.5 EMERGENCY EQUIPMENT The CRN Site maintains supplies of emergency equipment located in designated storage locations. The CRN Site implements site-specific procedures to ensure required calibrations are carried out on a routine basis. Reference Appendix A, Attachment 2 for additional information regarding emergency equipment and supplies.
A.4.5.1 Emergency Communications Equipment Information regarding the CRN Site Emergency Communications Equipment is addressed in the CRN Site COLA.
A.4.5.2 First Aid and Medical Facilities A.4.5.2.1 Decontamination Facilities The site maintains supplies and equipment as needed to establish a temporary decontamination area for the purpose of gross radiological decontamination and injured person evaluation and stabilization. Equipment and materials for decontamination and first aid, including a stretcher, are available.
A.4.5.2.2 First Aid Stations and Supplies Emergency medical equipment is strategically located throughout the plant, with trauma kits and other specified equipment available for use by the Medical Emergency Response Team (MERT).
Emergency Medical Technicians (EMTs) provide first aid for injured individuals. Medical supplies and treatment for minor injuries are available. First aid treatment is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.
Rad Protection stores and controls potassium iodide (KI) tablets for onsite personnel. CRN-EPIPs provide usage information, including information addressing authorization for use and dispersal of tablets.
A.4.5.2.3 Receiving Hospitals and Supplies TVA maintains arrangements with local medical facilities to receive patients from the CRN Site.
A.4.5.2.4 Ambulance Service TVA maintains an ambulance, staffed in conjunction with the MERT, at the site. TVA also maintains arrangements for offsite ambulance assistance to the CRN Site.
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Appendix A A.4.6 ADDITIONAL LOCAL SUPPORT A.4.6.1 Fire TVA maintains arrangements for local firefighting support upon request. The senior offsite fire official responding to the CRN Site coordinates response activities with the TVA Incident Commander. The CRN Site is responsible for providing radiological protection and proper safety clearance in affected areas.
A.4.6.2 Law Enforcement TVA maintains agreements with local law enforcement agencies to provide law enforcement support when necessary.
A.4.6.3 Vendor Support If necessary, the Nuclear Steam Supply System (NSSS) vendor will be contacted by the Central Emergency Control Center (CECC) to provide assistance in the form of manpower, equipment, and technical backup. Other vendors will also be contacted if their assistance is needed.
A.4.7 ASSEMBLY/ACCOUNTABILITY ALARM TVA maintains warning signals to alert onsite personnel of hazards and the need for assembly or evacuation.
A.4.8 LOCAL RECOVERY CENTER The CRN Site has a Local Recovery Center (LRC) which is a pre-designated facility dedicated for use by offsite TVA and NRC personnel that may be assigned to the CRN Site for recovery operations. In addition, the LRC may be used by the NRC during the event as an area near the site for assessment and assistance and has the capability to communicate offsite. Personnel in the LRC have access to necessary drawings and documents. Meteorological information is available in the LRC. The LRC may serve as an alternate emergency response facility, as needed, and during an emergency, may be used as a staging location for personnel prior to dispatch to the CRN Site.
Personnel in the LRC have access to necessary drawings, manuals, procedures and documents. Meteorological information and dose rate calculations are available in the LRC. The LRC has telephone communications capabilities to enable personnel to communicate with the CECC and the CRN Site TSC. The LRC is able to send and receive data and document production / reproduction equipment is available.
The location, function, and capabilities of the LRC is addressed in the CRN Site COLA.
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Appendix A A.5 MAINTAINING EMERGENCY PREPAREDNESS A.5.1 RESPONSIBILITY FOR THE EMERGENCY PREPAREDNESS EFFORT The Site Vice President maintains overall authority and responsibility for radiological emergency response planning. The Director, Emergency Preparedness is assigned responsibility for coordinating emergency preparedness efforts, including activities related to the development of emergency plans and procedures and coordinating the plans and procedures with supporting organizations to ensure the overall effectiveness of the program.
A.5.2 PROCEDURES The CRN Site maintains a range of emergency plan implementing procedures (CRN-EPIPs) that provide instructions for implementing the emergency response measures described in the site Emergency Plan. Part 5A Section 16 provides a description of the CRN-EPIP document control, approval and revision processes.
A.5.3 INDEPENDENT REVIEWS OF EMERGENCY PREPAREDNESS TVAs independent Quality Assurance organization performs, or oversees the performance of, periodic independent audits of the emergency preparedness program consistent with the requirements of 10 CFR 50.54(t). The audits include, at a minimum, the following:
- The Emergency Plan.
- EPIPs and practices.
- The emergency preparedness training program.
- Readiness testing (e.g., drills and exercises).
- Emergency response facilities, equipment, and supplies.
- Interfaces with State and local government agencies.
- Required records and documentation.
TVAs independent Quality Assurance organization documents audit results and improvement recommendations and reports these results to the CRN Site and TVA management. TVA establishes and maintains the frequency of the periodic audits based on an assessment of performance as compared to performance indicators; however, the audit frequency is not less than once every 24 months. In addition, TVA conducts a program audit as soon as reasonably practicable after a change occurs in personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but no longer than twelve months after the change.
TVA makes those portions of the audits that address the adequacy of interfaces with State and local governments available to the affected governments.
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Appendix A A.6 ALERT AND NOTIFICATION SYSTEM (NOT APPLICABLE)
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Appendix A A.7 TRAINING AND DRILLS A.7.1 TRAINING PERSONNEL Personnel with specific duties and responsibilities in the CRN Site Radiological Emergency Preparedness (REP) program receive instruction in the performance of their duties and responsibilities in accordance with CRN Site training procedures, and as required in ESPA Part 5A Section 15.
A.7.2 DRILLS AND EXERCISES TVA conducts drills and exercises to develop and maintain the key skills that are required for emergency response. TVA may conduct the drills identified in ESPA Part 5A Section 14 individually or as part of a REP exercise.
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Appendix A A.8 EMERGENCY PLAN IMPLEMENTING PROCEDURES The range of actions needed to implement the contents of this Plan are found in the CRN-EPIPs, which, at a minimum, address the following topics:
- Emergency Classification
- Notifications Associated with Emergency Conditions
- Emergency Communications
- Onsite Protective Action Recommendations
- Activation of the Emergency Response Organization
- Staffing and Operation of Emergency Response Facilities
- Site Assembly, Accountability, and Evacuation
- Core Damage Assessment
- Radiation Protection Under Emergency Conditions
- Plume Tracking and Assessment of Radiological Conditions
- Respiratory Protection and Distribution of Radioprotective Drugs
- Personnel Monitoring
- Decontamination
- Obtaining and Analyzing High Activity Samples Under Emergency Conditions
- Emergency Media Relations
- Recovery and Reentry Additional plant procedures address various activities that are required to support the ongoing maintenance of the EP program. These supporting procedures are not included within the body of the EPIPs. These supporting procedures address, at a minimum, the following topics:
- Emergency Equipment and Communications Systems Inventory and Operational Tests
- Conduct of Emergency Drills and Exercises
- Emergency Plan Training
- Maintaining Emergency Preparedness A-21 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A Attachment 1 STATE MULTIJURISDICTIONAL RADIOLOGICAL EMERGENCY RESPONSE PLAN The State of Tennessee Multijurisdictional Radiological Emergency Response Plan is maintained in the CECC and the CRN Site TSC.
A-22 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A Attachment 2 EMERGENCY EQUIPMENT AND SUPPLIES TVA establishes and maintains inventories of emergency equipment and supplies for use by emergency response personnel in the emergency response facilities and by TVA field monitoring teams. The actual inventories are based on the activities that occur in, or are dispatched from, each individual facility. Actual inventories are established in inventory lists in accordance with EPIPs. Emergency kit inventories typically include the following:
- Radiation survey instrument(s).
- Surface contamination control and survey supplies.
- Air sampling equipment and sampling media.
- Scaler(s) or other appropriate radio-analytical counting instrument(s).
- Protective clothing.
- Contamination control and decontamination supplies.
- Respiratory protection equipment.
- Radiological control posting and warning supplies.
- Personnel monitoring equipment (record and instantaneous reading dosimeters).
- Radioiodine blocking agent.
- Emergency lighting equipment.
- Appropriate maps.
- Computer equipment.
- Administrative and recordkeeping supplies.
- Plans, procedures, and drawings.
- Communications equipment.
- Batteries and other expendable supplies.
- First aid supplies (e.g., bandages, stretchers, splints, topical ointments).
A-23 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A Attachment 3 CROSS REFERENCE TO REGULATIONS AND GUIDANCE NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions 10 CFR 52.17(b)(1) N/A No known physical characteristics /
impediments to development of emergency plans.
10 CFR 52.17(b)(2)(i) N/A All (major features emergency plan) 10 CFR 52.17(b)(3) N/A Emergency Preparedness Inspections, Tests, Analysis and Acceptance Criteria (EP-ITAAC) 10 CFR 52.17(b)(4) N/A 16.5 10 CFR 50.72(a)(4) N/A A.4.4.5 10 CFR 50.72(c)(3) N/A 3.2, 6.4, 8.1.1, 8.2 10 CFR 50.47(b)(1) A.1.a 3.3, 3.3.24, 3.3.25, 3.3.26, 3.3.27, 10 CFR 50 App E.IV.A A.4.5.2, A.4.6 A.1.b 2.3, 3.1, 3.2, 3.3, A.3 A.1.c Figure 3-1, Figure A.3-1, Figure A.3-2 A.1.d 3.2, A.3 A.1.e 3.2, 5.2, A.3 A.2.a N/A A.2.b N/A A.3 16.5 A.4 3.2, A.5.1 10 CFR 50.47(b)(2) B.1 3.2, A.3 10 CFR 50 App E.IV.A 10 CFR 50 App E.IV.H B.2 3.2, A.3.6.2 B.3 3.2 A-24 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions B.4 3.2, A.3.6.2 B.5 3.1.1, 3.2, 3.3, Figure 3-1, A.3, Figure A.3-1, Figure A.3-2 B.6 Figure 3-1, Figure A.3-1, Figure A.3-2 B.7 3.2, A.3 B.7.a 3.3.23 B.7.b 13.0 B.7.c 3.2, A.3.6.1 B.7.d 3.3.1, 3.3.13, 7.0, 7.1, 7.2, 7.3, 7.4 B.8 3.3.26, A.4.6.3 B.9 Figure 2-1, 3.3.24, 12.2, 12.3, 12.4, A.4.5, A.4.6 10 CFR 50.47(b)(3) C.1.a 2.4 10 CFR 50 App E.IV.A C.1.b 2.4, 3.3.25 C.1.c 1.0, 6.0, 6.1, 6.2, 6.4, 6.7, 6.8, 8.1, 13.3, A.4.8 C.2.a N/A C.2.b 3.3.7, 5.2.3, 5.2.4 C.3 9.2.2, 9.2.3, A.4.3 C.4. 2.4, 3.3.24 - 3.3.26, 9.2, 12.4, 16.5, A.4.6, 10 CFR 50.47(b)(4) D.1 4.1, 4.2, A.2 10 CFR 50 App E.IV.B D.2 A.2 D.3 N/A A-25 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions D.4 N/A 10 CFR 50.47(b)(5) E.1 5.0, 5.1, 5.2 (all), Figure 5-1 10 CFR 50 App E.IV.C 10 CFR 50 App E.IV.D E.2 3.3.5, 3.3.6, 5.0, 5.1, 5.2 (all), Figure 5-1 E.3 5.0, 5.2 E.4 5.0, 5.2 (details described in EPIPs)
E.4.a 5.0, 5.2 (details described in EPIPs)
E.4.b 5.0, 5.2 (details described in EPIPs)
E.4.c 5.0, 5.2 (details described in EPIPs)
E.4.d 5.0, 5.2 (details described in EPIPs)
E.4.e 5.0, 5.2 (details described in EPIPs)
E.4.f 5.0, 5.2 (details described in EPIPs)
E.4.g 5.0, 5.2 (details described in EPIPs)
E.4.h 5.0, 5.2 (details described in EPIPs)
E.4.i 5.0, 5.2 (details described in EPIPs)
E.4.j 5.0, 5.2 (details described in EPIPs)
E.4.k 5.0, 5.2 (details described in EPIPs)
E.4.l 5.0, 5.2 (details described in EPIPs)
E.4.m 5.0, 5.2 (details described in EPIPs)
E.4.n 5.0, 5.2 (details described in EPIPs)
E.5 N/A E.6 N/A E.7 N/A A-26 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions 10 CFR 50.47(b)(6) F.1.a 3.2, 5.2, 6.0, 6.1, 6.2, 6.4, 6.7, A.3, 10 CFR 50.72(a)(3) A.4.5.1, F.1.b 3.3.4, 6.4, A.4.5.1 F.1.c 3.2, 6.4, A.4.5.1 F.1.d 6.0, 6.1, 6.2, 6.4, 6.7, A.4.5.1 F.1.e 6.5, 6.6, A.4.5.1 F.1.f 6.0, 6.4, A.4.5.1 F.2 6.0, 6.1, 6.2, 6.4, 6.8, A.4.5.1 F.3 6.0, 6.4, A.4.5.1 10 CFR 50.47(b)(7) G.1 7.0, 7.1, 7.2, 7.2.4, 7.5 10 CFR 50 App E.IV.D G.2 7.0, 7.1, 7.2, 7.2.4, 7.5 G.3.a 3.3.13, 7.0, 7.1, 7.2.1 - 7.2.4, 7.3, 7.4 G.3.b 7.3 G.4.a 3.3.13, 7.2.1 - 7.2.4 G.4.b 7.4 G.4.c 7.7 G.5 7.8 10 CFR 50.47(b)(8) H.1 8.0, 8.1, A.4, A.4.1, A.4.2 10 CFR 50 App E.IV.E H.2 Figure 8-1, 8.2 H.3 N/A H.4 Figure 3-1, 3.3, 6.0, 6.3, 6.5, 6.6 H.5 A.4.4 H.5.a 9.2.4 (all), A.4.4.1 A-27 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions H.5.b A.4.4.2 (all)
H.5.c A.4.4.3 H.5.d A.4.4.6 H.6.a 9.2.4 (all), A.4.4.1 H.6.b 11.0, Appendix A (Attachment 2)
H.6.c 9.2.3 H.7 9.2.2 H.8 9.2.4 (all), A.4.4.1 H.9 8.1.2, A.4.2 H.10 A.7 (EPIP list), Appendix A (Attachment 2)
H.11 Appendix A (Attachment 2)
H.12 8.2, 8.3 10 CFR 50.47(b)(9) I.1 9.0 (all)
I.2 9.1 I.3.a 9.2.5 I.3.b 9.2.5 I.4 9.2.4, 9.2.5 I.5 9.2.4 I.6 9.2.5 I.7 9.2.2 I.8 9.2.2 I.9 9.2.2 A-28 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions I.10 9.2.2, 9.2.5 I.11 N/A 10 CFR 50.47(b)(10) J.1.a 10.1, A.4.7 J.1.b 10.1, A.4.7 J.1.c 10.1, A.4.7 J.1.d 10.1, A.4.7 J.2 10.1, A.4.7 J.3 10.1 J.4 10.1 J.5 10.1, A.4.7 J.6.a 10.1, 11.0 (all)
J.6.b 10.1, 11.0 (all)
J.6.c 10.1, 11.0 (all)
J.7 10.3, Figure 10-1 J.8 N/A J.9 N/A J.10.a N/A J.10.b N/A J.10.c N/A J.10.d N/A J.10.e N/A J.10.f N/A A-29 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions J.10.g N/A J.10.h N/A J.10.i N/A J.10.j N/A J.10.k N/A J.10.l N/A J.10.m N/A J.11 N/A J.12 N/A 10 CFR 50.47(b)(11) K.1.a 12.0, 12.1, 12.2 (all), 12.4 K.1.b 12.0, 12.1, 12.2 (all), 12.4 K.1.c 12.0, 12.1, 12.2 (all), 12.4 K.1.d 12.0, 12.1, 12.2 (all), 12.4 K.1.e 12.0, 12.1, 12.2 (all), 12.4 K.1.f 12.0, 12.1, 12.2 (all), 12.4 K.1.g 12.0, 12.1, 12.2 (all), 12.4 K.2 11.0, Table 11-1, Table 11-2 K.3.a 11.0 K.3.b 11.0 K.4 N/A K.5.a 11.0, 12.1, 12.2.3, A.4.5.2.1 K.5.b 11.0, 12.1, 12.2.3, A.4.5.2.1 A-30 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions K.6.a 11.0 K.6.b 11.0 K.6.c 11.0 K.7 11.0, 12.2.3, A.4.5.2.1 10 CFR 50.47(b)(12) L.1 12.4 L.2 12.1, A.4.5.2.2 L.3 N/A L.4 12.3, A.4.5.2.4 10 CFR 50.47(b)(13) M.1 13.1, Figure 13-1, 13.2 (all), 13.3, 13.4, 10 CFR 50 App E.IV.H A.4.8 M.2 Figure 13-1, 13.2 (all)
M.3 13.1 M.4 N/A 10 CFR 50.47(b)(14) N.1.a 14.2, A.6.2 N.1.b 14.2, A.6.2 N.2.a 14.1.7, A.6.2 N.2.b 14.1.6, A.6.2 N.2.c 14.1.1, A.6.2 N.2.d 14.1.2, A.6.2 N.2.e(1) 14.1.3, A.6.2 N.2.e(2) 14.1.4, A.6.2 N.3.a 14.3, A.6.2 N.3.b 14.3, A.6.2 A-31 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions N.3.c 14.3, A.6.2 N.3.d 14.3, A.6.2 N.3.e 14.3, A.6.2 N.3.f 14.4, A.6.2 N.4 14.4, A.6.2 N.5 14.4, A.6.2 10 CFR 50.47(b)(15) O.1 15.0, 15.1, 15.2, 15.3, A.6.1 10 CFR 50 App E.IV.F O.1.a 15.2, A.6.1 O.1.b N/A O.2 15.1, A.6.1 O.3 15.1, A.6.1 O.4.a 15.0, 15.1, A.6.1 O.4.b 15.0, 15.1, A.6.1 O.4.c 15.0, 15.1, A.6.1 O.4.d 15.0, 15.1, A.6.1 O.4.e 15.0, 15.1, A.6.1 O.4.f 15.0, 15.1, A.6.1 O.4.g 15.0, 15.1, A.6.1 O.4.h 15.0, 15.1, A.6.1 O.4.i 15.0, 15.1, A.6.1 O.4.j 15.0, 15.1, A.6.1 O.5 15.0, 15.1, 15.2, A.6.1 A-32 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5A, Emergency Plan (Site Boundary EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions 10 CFR 50.47(b)(16) P.1 15.3, A.6.1 10 CFR 50 App E.IV 10 CFR 50 App E.IV.G P.2 A.5.1 P.3 A.5.1 P.4 A.5.1, A.5.2 P.5 16.1, 16.2 (all)
P.6 Appendix A (Attachment 1)
P.7 9.2.1, A.7 P.8 Table of Contents (Generic Part), Table of Contents (Appendix A), Appendix A (Attachment 3)
P.9 16.4, A.5.3 P.10 16.2.2 A-33 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B Emergency Plan (2-Mile EPZ)
Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Table of Contents 1.0 PURPOSE ....................................................................................................... 1 2.0 SCOPE ............................................................................................................ 3 2.1 APPENDICES ................................................................................................. 3 2.2 IMPLEMENTING PROCEDURES ................................................................... 3 2.3 STATE RADIOLOGICAL EMERGENCY PLAN ............................................. 4 2.4 NATIONAL RESPONSE FRAMEWORK ........................................................ 5 3.0 PROCESS ....................................................................................................... 6 3.1 ROLES AND RESPONSIBILITIES ................................................................. 6 3.1.1 Emergency Management Organization (Concept of Operations) ............. 6 3.2 ONSITE ORGANIZATION .............................................................................. 6 3.3 OFFSITE ORGANIZATION ............................................................................. 7 3.3.1 CECC Director................................................................................................ 8 3.3.2 Assistant CECC Director .............................................................................. 8 3.3.3 Emergency Preparedness Staff Representative ......................................... 8 3.3.4 State Communicator ..................................................................................... 8 3.3.5 TVA Operations Duty Specialist ................................................................... 9 3.3.6 Emergency Duty Officer ................................................................................ 9 3.3.7 TVA State Liaison .......................................................................................... 9 3.3.8 CECC Plant Assessment Manager ............................................................... 9 3.3.9 Plant Assessment Coordinator .................................................................. 10 3.3.10 CECC Plant Assessment Team .................................................................. 10 3.3.11 Resource Support Coordinator .................................................................. 10 3.3.12 Engineering Representative ....................................................................... 10 3.3.13 Public Information Manager ....................................................................... 11 3.3.14 JIC Liaison ................................................................................................... 11 3.3.15 Public Information Writer ............................................................................ 11 3.3.16 Radiological Assessment Manager ........................................................... 11 3.3.17 Radiological Assessment Coordinator ..................................................... 12 3.3.18 Environmental Assessor ............................................................................ 12 3.3.19 Dose Assessor............................................................................................. 12 3.3.20 Meteorologist ............................................................................................... 13 3.3.21 Technical Advisors...................................................................................... 13 3.3.22 Boardwriter(s) .............................................................................................. 13 ii Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 3.3.23 Management Services ................................................................................. 13 3.3.24 Local Support .............................................................................................. 14 3.3.25 Federal Agency Support ............................................................................. 14 3.3.26 Vendor Support ........................................................................................... 14 3.3.27 INPO .............................................................................................................. 14 4.0 EMERGENCY CONDITIONS ........................................................................ 16 4.1 CLASSIFICATION SYSTEM ......................................................................... 16 4.1.1 NOUE ............................................................................................................ 16 4.1.2 Alert .............................................................................................................. 16 4.1.3 Site Area Emergency................................................................................... 17 4.1.4 General Emergency ..................................................................................... 17 4.2 IDENTIFICATION OF EMERGENCY CLASSES .......................................... 18 5.0 EMERGENCY NOTIFICATION AND ACTIVATION OF PLAN .................... 19 5.1 ONSITE ......................................................................................................... 19 5.2 OFFSITE ....................................................................................................... 19 5.2.1 NOUE ............................................................................................................ 19 5.2.2 Alert .............................................................................................................. 20 5.2.3 Site Area Emergency................................................................................... 21 5.2.4 General Emergency ..................................................................................... 21 6.0 COMMUNICATIONS ..................................................................................... 23 6.1 EP TELEPHONE SYSTEM ........................................................................... 23 6.2 PLANT TELEPHONE SWITCHING EQUIPMENT ........................................ 23 6.3 PLANT OR BUILDING LOUDSPEAKER PAGING ...................................... 23 6.4 OFFSITE TELEPHONE COMMUNICATIONS .............................................. 23 6.5 EP NOTIFICATION SYSTEM ....................................................................... 24 6.6 TVA ENTERPRISE EMERGENCY NOTIFICATION SYSTEM ..................... 24 6.7 EP RADIO SYSTEM ..................................................................................... 24 6.8 OTHER RADIO COMMUNICATIONS ........................................................... 24 7.0 PUBLIC INFORMATION AND EDUCATION ................................................ 25 7.1 PURPOSE ..................................................................................................... 25 7.2 RESPONSIBILITIES ..................................................................................... 25 7.2.1 CECC Director.............................................................................................. 25 7.2.2 JIC Spokesperson ....................................................................................... 25 7.2.3 Director, Public Relations & Corporate Information ................................ 25 iii Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 7.2.4 Operations Communications ..................................................................... 25 7.3 PUBLIC INFORMATION FACILITIES .......................................................... 26 7.4 COORDINATION OF INFORMATION .......................................................... 26 7.5 PUBLIC EDUCATION ................................................................................... 26 7.6 EMPLOYEE COMMUNICATIONS ................................................................ 26 7.7 RUMOR CONTROL/PUBLIC INFORMATION ............................................. 26 7.8 TRAINING ..................................................................................................... 26 8.0 EMERGENCY RESPONSE FACILITIES, EQUIPMENT, AND SUPPLIES .. 27 8.1 NUCLEAR SITE FACILITIES ....................................................................... 27 8.1.1 Technical Support Center ........................................................................... 27 8.1.2 Operations Support Center ........................................................................ 27 8.1.3 Local Recovery Center ................................................................................ 27 8.1.4 Site Decontamination Facilities ................................................................. 28 8.1.5 Equipment, Supplies, and Supplemental Data ......................................... 28 8.2 CENTRAL EMERGENCY CONTROL CENTER ........................................... 28 8.3 RADIOLOGICAL MONITORING CONTROL CENTER ................................ 29 8.4 JOINT INFORMATION CENTER .................................................................. 29 8.5 ALERT AND NOTIFICATION SYSTEM ....................................................... 29 9.0 ACCIDENT ASSESSMENT .......................................................................... 31 9.1 ONSITE ......................................................................................................... 31 9.2 OFFSITE ....................................................................................................... 31 9.2.1 General Information .................................................................................... 31 9.2.2 Sampling Team ............................................................................................ 33 9.2.3 Analyzing Environmental Samples ............................................................ 34 9.2.4 Meteorological Information ........................................................................ 34 9.2.5 Dose Assessment........................................................................................ 35 10.0 PROTECTIVE RESPONSE ........................................................................... 36 10.1 ONSITE PROTECTIVE ACTIONS FOR RADIOLOGICAL EVENTS ........... 36 10.2 ONSITE PROTECTIVE ACTIONS FOR HOSTILE ACTION EVENTS ......... 37 10.3 OFFSITE ....................................................................................................... 37 11.0 RADIOLOGICAL PROTECTION .................................................................. 39 12.0 MEDICAL SUPPORT .................................................................................... 43 12.1 GENERAL INFORMATION ........................................................................... 43 iv Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 12.2 CLASSIFICATION AND HANDLING OF MEDICAL EMERGENCY PATIENTS ..................................................................................................... 43 12.2.1 Noncontaminated-Nonirradiated ................................................................ 43 12.2.2 Irradiated-Noncontaminated ....................................................................... 43 12.2.3 Contaminated............................................................................................... 44 12.3 TRANSPORTATION OF INJURED PERSONNEL ....................................... 44 12.4 INTERAGENCY ASSISTANCE FROM REAC/TS ........................................ 44 13.0 TERMINATION AND RECOVERY ................................................................ 45 13.1 TERMINATION .............................................................................................. 45 13.2 RECOVERY ORGANIZATION ...................................................................... 47 13.2.1 Chief Nuclear Officer ................................................................................... 47 13.2.2 Senior Vice President Operations .............................................................. 47 13.2.3 Site Vice President ...................................................................................... 47 13.2.4 Vice President, Operations Support .......................................................... 47 13.2.5 CECC Public Information Manager ............................................................ 48 13.2.6 Vice President, Nuclear Licensing ............................................................. 48 13.2.7 Vice President, Engineering & Support ..................................................... 48 13.2.8 Vice President, Nuclear Oversight ............................................................. 48 13.2.9 Other TVA Resources ................................................................................. 48 13.3 ONSITE RECOVERY .................................................................................... 48 13.4 LOCAL RECOVERY CENTER ..................................................................... 49 13.5 OFFSITE RECOVERY .................................................................................. 49 14.0 DRILLS AND EXERCISES ........................................................................... 50 14.1 DRILLS.......................................................................................................... 50 14.1.1 Medical Emergency Drills ........................................................................... 50 14.1.2 Radiological Monitoring Drills .................................................................... 50 14.1.3 Rad Protection Drills ................................................................................... 50 14.1.4 Radio Chemistry Drills ................................................................................ 50 14.1.5 Radiological Dose Assessment ................................................................. 50 14.1.6 Fire Drills ...................................................................................................... 50 14.1.7 Communications Drills ............................................................................... 51 14.2 EXERCISES .................................................................................................. 51 14.3 SCENARIOS ................................................................................................. 51 14.4 CRITIQUES ................................................................................................... 52 v Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 15.0 TRAINING ..................................................................................................... 53 15.1 ONSITE ......................................................................................................... 53 15.2 OFFSITE ....................................................................................................... 53 15.3 PROFESSIONAL DEVELOPMENT TRAINING ........................................... 53 16.0 PLAN MAINTENANCE ................................................................................. 54 16.1 NP-REP ......................................................................................................... 54 16.2 EPIPs ............................................................................................................ 55 16.2.1 Document Identification .............................................................................. 55 16.2.2 Periodic Review ........................................................................................... 57 16.2.3 EPIP Changes .............................................................................................. 57 16.2.4 Distribution .................................................................................................. 59 16.3 DOCUMENT RELATIONSHIPS .................................................................... 59 16.4 AUDITS ......................................................................................................... 59 16.5 AGREEMENT LETTERS .............................................................................. 60 17.0 DEFINITIONS AND ACRONYMS ................................................................. 61 Justification for the Central Emergency Control Center.66 Appendix A Emergency Plan (2-Mile EPZ)
SUPPLEMENTAL INFORMATION Evacuation Time Estimate Report vi Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 1.0 PURPOSE The purpose of Part 5B is to provide sufficient information to ensure the compatibility of the proposed emergency plans (for both onsite areas and the plume exposure and ingestion exposure pathway emergency planning zones) with facility design features, site layout, and site location. Part 5B, in conjunction with the Evacuation Time Estimate Report, addresses considerations such as access routes, population distributions, land use, and local jurisdictional boundaries. In an effort to maintain consistency throughout the fleet, the content of Part 5B is based on the Tennessee Valley Authoritys (TVA) Nuclear Power Radiological Emergency Plan (NP-REP), Generic Part, which has been approved by the U.S. Nuclear Regulatory Commission (NRC) for use at all of the TVA operating nuclear facilities. Site-specific information is included in Appendix A to this Plan to address emergency planning for the Clinch River Nuclear (CRN) Site. This Plan addresses pertinent requirements and associated guidance contained in NUREG-0654, Revision 1, Supplement 2, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants - Criteria for Planning in an Early Site Permit Application (NUREG-0654 Supplement 2), to provide major features of the Emergency Plan. Information that was not available to TVA during the development of the CRN Site Early Site Permit Application (ESPA) will be addressed in the Combined License Application (COLA). Information to be addressed at COLA includes analysis normally found in a Design Certification Application and not currently available such as specific accident development details, staffing levels, required safety-related equipment.
In accordance with 10 CFR Part 52, Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants, Part 5B addresses the emergency planning requirements of Appendix E to 10 CFR Part 50, Section III, the Final Safety Analysis Report; Site Safety Analysis Report. Part 50 Appendix E states, The final safety analysis report or the site safety analysis report for an early site permit that includes major features of emergency plans under 10 CFR 52.17(b)(2)(i) of this chapter shall contain the plans for coping with emergencies. In addition, these regulations require that the application must contain the means which the standards of § 50.47(b) will be met.
In the development of this Plan, TVA has considered the applicable guidance provided in the following documents with consideration given to the proposed exemptions contained in Part 6 of the ESPA:
- NUREG-0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (NUREG-0654).
- NUREG-0654, Revision 1, Supplement 2.
- NUREG-0654, Revision 1, Supplement 3, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants - Guidance for Protective Action Strategies (NUREG-0654).
- Regulatory Guide 1.101, Revision 3, Emergency Planning and Preparedness for Nuclear Power Reactors (RG 1.101).
1 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
- Section 13.3 of Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) (RG 1.70).
- Section 13.3 of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-0800).
As specified in NUREG-0654 and RG 1.101, this Plan provides for the following:
- Adequate measures are taken to protect employees and the public.
- Individuals having responsibilities during an emergency are properly trained.
- Procedures exist to provide the capability to cope with a spectrum of emergencies ranging from those of little consequence to major core melt.
- Equipment is available to detect, assess, and mitigate the consequences of such occurrences.
- Emergency action levels and procedures are established to assist in making decisions.
This Plan has been developed to respond to potential radiological emergencies at the CRN Site as they may apply to small modular reactors (SMRs). As discussed in Site Safety Analysis Report (SSAR) Section 13.3 of this EPSA, the SMR technologies under consideration do not have postulated design basis accidents that would result in dose consequences that are large enough to require offsite emergency planning, the overall scope of this plan delineates the actions necessary to safeguard onsite personnel (within the site boundary) and minimize damage to property. As discussed in Part 3 of this ESPA, for postulated beyond design basis accidents, analysis has concluded that, because of the slow progression rate, sufficient time is available to initiate appropriate mitigating actions to protect the health and safety of the public beyond the Site Boundary.
The NRC requires a level of emergency preparedness commensurate with the potential consequences to public health, safety, common defense, and security at the CRN Site. This Plan considers the proposed exemptions contained in Part 6 of the ESPA. Implementation of this Plan is not dependent on the comprehensive emergency management plan (CEMP) nor would TVA impose a requirement on offsite agencies to implement this Plan.
The CRN Site ESPA (Part 5B, Emergency Plan) consists of this Generic Part and the site specific Appendix A. Appendix A is complementary with the State plan referenced in Appendix A, Attachment 1.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 2.0 SCOPE This Plan provides information regarding emergency preparedness and response planning for the CRN Site and addresses organizational responsibilities, capabilities, actions, and guidelines for TVA during a radiological emergency. It also describes the centralized emergency management concept which was approved by the NRC Commissioners via COMJA-80-37 (January 21, 1981). Additional guidance regarding the centralized emergency management concept can also be found in NRC SECY-96-170 (August 5, 1996) and NRC SECY-10-0078 (June 16, 2010).
2.1 APPENDICES Additional Radiological Emergency Plan information specific to the CRN Site is included as the CRN Site ESPA (Part 5B, Emergency Plan / Appendix A); referred to in the remainder of this document as Appendix A.
Appendix A details facility features, capabilities, equipment, and responsibilities. The Generic Part together with Appendix A, describes the methods TVA will use to:
- 1. Detect an emergency condition.
- 2. Evaluate the severity of the problems.
- 3. Notify federal, State, and local agencies of the condition.
- 4. Activate emergency organizations.
- 5. Evaluate the possible offsite consequences.
- 6. Recommend protective actions for the public.
- 7. Mitigate the consequences of the emergency.
Since TVAs authority is limited to TVA-owned and controlled property, the State of Tennessee (State) and local agencies are responsible for ordering and implementing actions offsite to protect the health and safety of the public. Appendix A, Attachment 1 references the State Plan which supplements this Plan.
2.2 IMPLEMENTING PROCEDURES TVA develops specific procedures to ensure that the Plan is implemented as designed. These implementing procedures are designed to ensure that emergencies are properly evaluated, rapid notifications made, and assessment and protective actions performed. These procedures are compiled in the Emergency Plan Implementing Procedures (EPIPs). Site specific procedures for abnormal and emergency operation and control exist but are not included in the EPIPs. These plant operating procedures are designed to ensure the implementation of the EPIPs.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 2.3 STATE RADIOLOGICAL EMERGENCY PLAN The State Radiological Emergency Plan is referenced in Appendix A, Attachment 1. This Plan provides for the coordinated response of the State and affected local governments as well as the States and local governments within the CRN Site ingestion exposure pathway Emergency Planning Zone (EPZ) and defines roles and responsibilities.
The responsibilities of these major organizations are summarized in Table 2-1.
Table 2-1 PRINCIPAL ORGANIZATIONAL RESPONSIBILITIES Local State TVA Command and Control X X X Warning X X X Notification Communications X X X Public Information X X X Emergency Assessment -- X X Public Health and Sanitation X X --
Social Services X -- --
Fire and Rescue X -- X Traffic Control X -- --
Emergency Medical Services X X X Law Enforcement X X --
Transportation X -- --
Protective Response X X --
Radiological Exposure Control X X X 4 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 2.4 NATIONAL RESPONSE FRAMEWORK The National Response Framework (NRF) Nuclear/ Radiological Incident Annex provides for timely, coordinated response by federal agencies to a fixed nuclear power plant facility incident.
The NRF is activated by either the affected State notifying the Department of Homeland Security (DHS), or the utility notifying the NRC of a radiological emergency at a nuclear plant site. The NRF is not included as part of the TVA Radiological Emergency Plan. Should additional radiological monitoring support be required, the appropriate State agency will make the request through DHS. The persons authorized to request this assistance, the specific resources expected, and resources available to support the federal response are provided in the respective State plans.
The NRF may be used by federal agencies in radiological emergencies. The NRF primarily concerns offsite federal response in support of State and local governments with jurisdiction for the emergency. The NRF provides the federal government's concept of operations for responding to radiological emergencies, outlines federal policies and planning assumptions, and specifies authorities and responsibilities of each federal agency that may have a significant role in such emergencies. The Central Emergency Control Center (CECC) Director is the TVA representative authorized to request federal assistance. Such a request from TVA will be made to the NRC.
TVA will utilize the CECC in Chattanooga Tennessee as the Emergency Operations Facility (EOF) for the Clinch River Nuclear Site. The CECC serves as the EOF for the other TVA nuclear plants (Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN)). This multi-site EOF was previously approved for use by the NRC in COMJA-80-37. Attachment 1 of this Plan provides additional description of and justification for the location of the CECC.
Because of the close proximity of the U.S. Department of Energy (DOE) Oak Ridge Reservation to the CRN Site, DOE response, should assistance be requested, is expected within 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Additional information about the NRF and available support is provided in NRC RIS 2005-13, NRC Incident Response and the National Response Plan (RIS 2005-13), NUREG-0728, Emergency Preparedness and Incident Response Programs (NUREG-0728) or the FEMA website (www.fema.gov) as well as in the Agency Emergency Response Plan (TVA-SPP-35.01).
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 3.0 PROCESS 3.1 ROLES AND RESPONSIBILITIES The development, implementation, and maintenance of the NP-REP is the responsibility of the TVA Nuclear organization. The General Manager, Support Services has delegated the authority for overall program control of the NP-REP to the Director, Emergency Preparedness as described below. Appendix A provides detailed staffing and organizational roles and responsibilities for the CRN Site minimum required Onsite Emergency Management Organization positions.
3.1.1 Emergency Management Organization (Concept of Operations)
The CRN Site Emergency Management Organization is divided into two categories; the Onsite Organization and the Offsite Emergency Organization. A block diagram of the Onsite Organization is presented in Appendix A and the Offsite Emergency Organization is presented in Figure 3-1. Emergency Management Organization personnel are required to participate in the Fitness for Duty Program.
The Onsite Organization is comprised of the Site Emergency Director (SED) and technical staff located in the Technical Support Center (TSC), a Control Room staff of Operations personnel, and additional support personnel located in the Operations Support Center (OSC). The Onsite Organization is responsible for the onsite response to an emergency condition. Onsite activities are directed by the SED to include such functions as Control Room operations, technical assessment, emergency mitigation analysis, onsite radiation surveys, and dose tracking for site personnel.
The Offsite Organization is designated as the CECC staff. The CECC staff is comprised of a CECC Director, a supporting group of technical assistants, and representatives of other TVA organizations. The CECC Director and supporting technical assistants report to the CECC during an emergency as required. Other TVA organizations will send representatives to the CECC as requested by the CECC Director.
The CECC is responsible for directing and coordinating the overall TVA response to an emergency condition. Functions such as offsite radiological monitoring and dose assessment, public information, State and local government coordination, and additional plant assessment are handled by the CECC relieving the Onsite Organization of the many peripheral duties necessary for the successful emergency response.
3.2 ONSITE ORGANIZATION Under normal conditions the Site Vice President is in charge of activities at the site and the Plant Manager is responsible for the safe efficient operation of the plant. The person primarily responsible for mitigation of an emergency is the SED. Upon declaration of an emergency the Shift Manager (SM) on duty initially fills the position of SED and directs emergency response from the Control Room. This position is transferred to the TSC when that facility is activated.
Once the TSC is activated, the SED and the TSC can provide technical support to the Control Room as part of their overall response to the emergency.
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The CRN Site is staffed on a continual 24-hour basis. The minimum staffing requirements for plant operations are established in the plant Technical Specifications. The staff responsibilities are as outlined in the SSAR, and are unchanged during an emergency. The on-shift composition listed in Appendix A may be less than the minimum requirements for a period of time in order to accommodate unexpected absences of personnel provided action is taken to restore the composition within established time requirements.
Under emergency conditions, the normal plant staff is supplemented as shown in Appendix A.
Appendix A also provides descriptions of the responsibilities of the personnel who augment the normal plant operating organization. Support personnel will be notified to report as required by the situation. Staffing time for the augmenting forces is indicated in Appendix A. This time could vary slightly, depending upon the time of day, weather conditions, immediate availability of personnel, and radiological conditions.
The Onsite Organization augments the shift operations crew. If members of the Onsite Organization are not present when an emergency occurs, the SM on-duty, or a designated Unit Supervisor when acting as the SM, is designated the SED and acts as such until relieved by the SED assigned to the TSC.
Upon detection of a known or suspected emergency, the SM on-duty refers to a CRN-EPIP to determine the classification of the emergency. After determining the classification of the incident, the SM assumes the responsibilities of SED and initiates the appropriate procedure referenced by the CRN-EPIP. Emergency communications / notifications with State, local and federal agencies, along with staffing instructions for the emergency response facilities are specified in CRN-EPIPs.
CRN-EPIPs designate personnel who staff the Emergency Notification System (ENS) and Health Physics Network (HPN) (NRC FTS 2000 System) Communication Systems. CRN-EPIPs also designate the interface with the NRC during TSC operation.
3.3 OFFSITE ORGANIZATION Figure 3-1 provides a diagram of the Offsite Organization, including those positions that must respond within a prescribed time of an Alert or higher (see Section 4.0, Emergency Conditions) emergency declaration at the CRN Site. The prescribed response times for the Offsite Organization will be addressed in the COLA.
Activation for the CECC is accomplished within a prescribed time following declaration of an Alert or higher (see Section 4.0, Emergency Conditions) emergency classification at the CRN Site, depending upon time of day, weather conditions, or immediate availability of personnel.
The prescribed activation time for the CECC for an event at the CRN Site will be addressed in the COLA.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 3.3.1 CECC Director The CECC Director has overall responsibility and authority for ensuring adequate TVA response to affected State/local governments in protecting the health and safety of the public. The CECC Director:
- Directs and coordinates TVA emergency response.
- Makes Protective Action Recommendations (PARs) to the State.
- Reviews and approves TVA press releases (excluding initial report of event).
- Reviews adequacy of information to news media/public.
- Acts as the primary point of contact for official TVA positions or recommendations.
- Ensures that key individuals are notified of the condition and severity of the events.
- Ensures information relative to the plant status, radiological impacts, and protective measures is available to emergency responders.
- Ensures NRC, U.S. Department of Energy (DOE), INPO, insurance underwriters, and the appropriate federal, State, and local agencies have been notified.
- Ensures points of contact for key types of information from the CECC are provided.
- Ensures 24-hour/day operations are established if required.
3.3.2 Assistant CECC Director An optional position that may be filled at the CECC Director's discretion to assist in carrying out duties. This position will be filled by a person qualified as CECC Director.
3.3.3 Emergency Preparedness Staff Representative The Emergency Preparedness (EP) Staff Representative:
- Advises the CECC Director regarding the NP-REP.
- Confirms the CECC is set up and operating properly.
- Assists the CECC Director in operating the CECC by evaluating, compiling, documenting, and posting data concerning the emergency situation.
3.3.4 State Communicator The State Communicator:
- Acts as the TVA primary communicator to the State.
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- Clarifies information discrepancies and ensures pertinent information related to plant status, onsite response, and TVA dose assessment is provided to the State.
- Further assists in providing TVA resource assistance, provides the State with technical advice as necessary, and assists the State Liaison (a State government representative) in briefings and coordinating responses to State inquiries.
3.3.5 TVA Operations Duty Specialist The position of Operations Duty Specialist (ODS) is staffed seven days a week, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.
After being notified of an emergency from the CRN Site, the ODS is responsible for making initial notification to the TVA REP Emergency Management Organization.
3.3.6 Emergency Duty Officer The Emergency Duty Officer (EDO) is responsible for establishing initial operation of the CECC in the event the NP-REP is activated at the Alert or higher (see Section 4.0, Emergency Conditions) emergency classification. The EDO is responsible for ensuring that appropriate initial notifications of TVA and offsite emergency organizations have been made for each emergency classification.
3.3.7 TVA State Liaison The TVA State Liaison acts as the CECC representative upon dispatch to the State Emergency Operations Center (SEOC) to interpret technical aspects of the emergency condition. He informs the CECC on State problems, requests, and actions.
3.3.8 CECC Plant Assessment Manager The CECC Plant Assessment Manager:
- Maintains contact with the SED or Technical Assessment Manager and ensures that necessary support is provided.
- Requests assistance from other TVA organizations or Nuclear Steam Supply System (NSSS) vendors as needed.
- Provides technical support for planning and reentry/recovery operations.
- Ensures the CECC Director is briefed on information pertaining to plant status and any protective actions indicated for the public based upon an assessment of plant status by the CECC and TSC assessment teams.
- Ensures that periodic status reports are received from the site and are provided to the CECC Director and other TVA support organizations.
- Makes recommendations to the SED on actions to be considered by the site to mitigate the problem based upon the assessment of plant status by the CECC Plant Assessment Team.
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The CECC Plant Assessment Manager is assisted by a Plant Assessment Team and additional support personnel who develop ongoing assessments of facility status and provide additional resource support.
3.3.9 Plant Assessment Coordinator The Plant Assessment Coordinator coordinates the plant status assessment activities in the Plant Assessment Area and directs overall plant assessment function and reports results to the Plant Assessment Manager. The plant information needed by the coordinator and plant assessment team is provided by a continuous telephone communications hookup with plant emergency staff.
3.3.10 CECC Plant Assessment Team The CECC Plant Assessment Team:
- Coordinates the decision to activate the Joint Information Center (JIC) with the CECC Director, the Director, Public Relations & Corporate Information, and SEOC if offsite officials elect to activate the SEOC.
- Provides a periodic evaluation of plant status information for input back to the TSC and the CECC Plant Assessment Manager. Members of the CECC Plant Assessment Team draw upon their knowledge of plant information, procedures, core damage assessment, and industry analysis to evaluate the assessments provided by the site in terms of current and long-range plant conditions. Results of evaluations and independent assessments provide the data needed for developing any necessary onsite protective actions.
- Serves as an engineering/operations/core damage assessment consultant for the plant and replies to plant inquiries based on the available information.
- Ensures that appropriate safety parameters are selected for trending and the CECC trend boards are maintained.
- Maintains a detailed log of the sequence of events during the emergency. Assists the CECC with other site-related communication needs, as necessary.
3.3.11 Resource Support Coordinator The Resource Support Coordinator maintains communications with other TVA Nuclear technical personnel to coordinate support as necessary; coordinates support from other TVA organizations such as legal, medical, finance, and procurement; and coordinates requests for support from other organizations outside TVA such as equipment vendors and INPO.
Coordinates arrangements for special equipment and supplies.
3.3.12 Engineering Representative The Engineering Representative provides a point of contact in the CECC for onsite and offsite engineering and provides engineering support as needed.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 3.3.13 Public Information Manager The Public Information Manager:
- Coordinates the decision to activate the Joint Information Center (JIC) with the CECC Director; the Director, Public Relations & Corporate Information; and SEOC if offsite officials elect to activate the SEOC.
- Ensures the JIC Spokesperson and the JIC Information Staff are provided information to inform the public and news media in response to an emergency.
- Coordinates news release drafts with the State and federal agencies participating at the JIC and secures approval of the CECC Director prior to making a release to the media.
- Directs the activities of support personnel who develop public information and maintain information flow into and from the JIC.
3.3.14 JIC Liaison The JIC Liaison contacts responding agencies and transmits information for coordination, and establishes and maintains an information flow from the JIC or Site Communications to the CECC.
3.3.15 Public Information Writer The Public Information Writer gathers information from the CECC personnel and Technical Advisor, prepares written statements based on that information, and develops information releases to be approved by the CECC Director for release to TVA employees.
3.3.16 Radiological Assessment Manager The Radiological Assessment Manager (RAM):
- Ensures that the CECC Director is briefed on matters concerning radiological conditions.
- Provides consultation, technical assistance, and obtains additional services as may be required for plant Rad Protection and offsite environmental radiological surveys.
- Ensures that radiological monitoring is conducted in the environment for areas potentially affected by the emergency and evaluates the radiological information to determine the extent of actual or probable hazard to the public or environment.
- Responsible for radiation dose management, including emergency dose authorizations, for personnel under their direction and control.
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- Provides technical support to the CECC Director for formulating protective actions for the public based on radiological conditions.
The RAM directs the activities of support personnel who coordinate collection and evaluation of radiological assessment data in the environs surrounding the facility.
3.3.17 Radiological Assessment Coordinator The Radiological Assessment Coordinator (RAC):
- Coordinates dose assessment, environs, and meteorological assessment activities in the Radiological Assessment Area (RAA) located in the CECC.
Ensures that information is provided to the TSC on dose projections, recommended offsite protective activities, environs measurements, and meteorological conditions.
- Directs the overall RAA function and communicates assessment results to the RAM.
- Ensures that information is provided to the TSC on dose projections, environs measurements, and meteorological conditions.
- Coordinates requests for additional Rad Protection equipment and personnel.
3.3.18 Environmental Assessor The Environmental Assessor:
- Coordinates requests for additional Rad Protection equipment and personnel.
- Performs monitoring and assessment activities for the TVA environs and coordinates the TVA field monitoring effort with the appropriate State agency regarding field monitoring activities.
- Coordinates the analysis of environs samples with the Western Area Radiological Laboratory (WARL).
- Provides technical support for planning and reentry/recovery operations.
- Coordinates with Dose Assessor regarding the results of the environmental assessments.
- Provides environmental monitoring results to the RAC or RAM for formulation of PARs to the CECC Director.
3.3.19 Dose Assessor The Dose Assessor:
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- Initiates and performs dose assessment activities during the radiological emergency and during the recovery and reentry phase.
- Consults with appropriate state agencies to resolve significant difference in assessments.
- Coordinates with the Environmental Assessor regarding the predicted position, exposure levels, concentrations, and duration of radiological effluents
- Provides dose assessment results to the RAC or RAM for formulation of protective action recommendations to the CECC Director.
3.3.20 Meteorologist The Meteorologist:
- Coordinates the analysis of environs samples with the Western Area Radiological Laboratory (WARL).
- Evaluating meteorological data and developing forecasts which may be used for dose assessment and other emergency preparedness activities.
- Reviews adequacy of observed data and replaces missing or invalid observations.
- Makes forecasts of dispersion conditions that affect radiological effluents.
- Provides dispersion knowledge to dose assessment staff.
- Prepares other meteorological forecasts needed for emergency preparedness activities.
3.3.21 Technical Advisors Technical Advisors provide technical assistance and explanation to the State Communicator, Public Information Staff, and Public Information Manager to ensure accurate information is released to the public and State agencies.
3.3.22 Boardwriter(s)
Boardwriters maintain the CECC Status Boards and EPZ maps with current information.
3.3.23 Management Services Management Services (MS) makes arrangements for and provides for clerical support, food and water, sanitary facilities, TVA transportation services, lodging, specialized equipment and supplies, communications, drawings, and controlled documents. MS is also authorized to issue checks for payment for emergency services to outside firms.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 3.3.24 Local Support TVA maintains agreements with police departments, fire departments, ambulance services, and hospitals near the CRN Site to provide appropriate services as requested.
3.3.25 Federal Agency Support TVA maintains an agreement with DOE Radiation Emergency Assistance Center/Training Site (REAC/TS), Oak Ridge, Tennessee. Other federal support would be requested through the NRF.
3.3.26 Vendor Support TVA may obtain technical support from the NSSS vendor during emergency situations. TVA may procure other vendor support as needed.
3.3.27 INPO TVA maintains an agreement with INPO, a consortium of nuclear utilities and other nuclear industries, to obtain any necessary support available from the industry during an emergency.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Central Federal Agency Support Emergency State and Local (Nuclear Regulatory Control Support (Emergency Commission /
Center Operations Centers) Department of 1
Director Homeland Security)
Emergency Duty Officer /
Directors Emergency Preparedness Aide 1 Staff Representative(s)
TVA Liaison to State Management Services Emergency Supervisor Operations Center Clerical Staff Operations Duty Technical Advisors Specialist Plant Public Site Radiological State Assessment Information Senior Vice 1 1
Emergency Assessment Communicator Manager Manager President 1 Director Manager Plant Joint Assessment Information Coordinator Center Liaison Technical Rad Support Assessment Center Coordinator Plant Information Assessment Writers Operations Team Environs Support Assessor Center Resource Support Coordinator Meteorologist 1
Dose Assessor 1
These Offsite Emergency Organization positions will be staffed within a prescribed time following an Alert or higher emergency declaration at the CRN Site. The prescribed time will be addressed in the CRN Site COLA.
Figure 3-1 Offsite Emergency Organization 15 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 4.0 EMERGENCY CONDITIONS 4.1 CLASSIFICATION SYSTEM TVA utilizes the following emergency classifications:
- Notification of Unusual Event (NOUE)
- Alert
- Site Area Emergency
- General Emergency This system of classification is consistent with the systems used by State and local emergency organizations. The emergency classifications are graded according to severity and immediate actions are taken to cope with the situation. Escalation to a higher class, or termination, occurs during the course of an emergency if warranted by conditions. Examples of plant conditions and their recommended emergency classes are given in the CRN-EPIPs. These procedures also specify the initial prompt notifications, information, and recommendations to be provided to State and local emergency organizations. Examples of Initiating Conditions (ICs) and specific instrument readings, if appropriate for the various classifications, are provided in the EPIPs.
4.1.1 NOUE This classification provides early and prompt notification of events that are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
The purposes of the NOUE are: (1) to ensure that the first steps in activating emergency organizations have been carried out; and (2) to provide current information on the unusual event.
TVA maintains the NOUE classification until closeout or escalation to a higher class. TVA notifies the State authorities and the NRC. The State notifies the local authorities. Following closeout, TVA provides a briefing to State authorities. TVA provides a written summary of significant events to the State no later than the next working day.
4.1.2 Alert An Alert classification is indicated when events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of Hostile Action. Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guides (PAG) exposure levels.
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The purposes of the Alert classification are: (1) to ensure that emergency personnel are readily available to respond if the situation becomes more serious or to perform confirmatory radiation monitoring, if required; and (2) to provide offsite authorities current status information.
TVA maintains the Alert class until event termination or escalation to a higher class. TVA notifies the State authorities and the NRC. The State notifies the local authorities. Following closeout, TVA provides a briefing to State authorities. TVA provides a written summary of significant events to the State no later than the next working day.
4.1.3 Site Area Emergency A Site Area Emergency is indicated when events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or Hostile Action that results in intentional damage or malicious acts: (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA PAG exposure levels beyond the site boundary.
The purposes of the Site Area Emergency classification are: (1) to ensure that emergency response centers are staffed; (2) to assure that monitoring teams are dispatched; (3) to assure that personnel required for evacuation of near-site areas are at duty stations if the situation becomes more serious; and (4) to provide current information for, and consultation with, offsite authorities and the public.
TVA maintains the Site Area Emergency classification until event termination or escalation to a higher class. TVA notifies the State authorities and the NRC. The State notifies the local authorities. Following closeout, TVA provides a briefing to State authorities. TVA provides a written summary of significant events to the State no later than the next working day.
4.1.4 General Emergency A General Emergency is indicated when events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or Hostile Action that results in an actual loss of physical control of the facility. Due to the SMR design, releases can be reasonably expected to exceed EPA PAG exposure levels offsite for more than the immediate site area.
The purposes of the General Emergency classification are: (1) to initiate predetermined protective actions for the public; (2) to provide continuous assessment of information from the site and offsite; and (3) to initiate additional measures as indicated by releases or potential releases of radioactivity.
When a General Emergency is declared, TVA recommends that State and local organizations implement protective actions as specified in the EPIPs.
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TVA maintains the General Emergency until event termination. TVA notifies the State authorities and the NRC. The State notifies local authorities unless the initial classification is General Emergency, in which case TVA initially notifies the local authorities. Following closeout, TVA provides a briefing to State authorities. TVA provides a written summary of significant events to the State no later than the next working day.
4.2 IDENTIFICATION OF EMERGENCY CLASSES TVA uses a variety of methods to identify emergency situations and to categorize them. As indicated in the CRN-EPIPs, emergencies can be caused by natural disasters such as tornadoes or floods, hazards such as aircraft crashes, releases of toxic gases, or breaches of plant security, as well as by conditions involving plant systems directly.
Recognition of the emergency class is primarily a judgment matter for plant personnel. The ICs used for recognizing and declaring the emergency class are based on specific measurable values or observable conditions defined as Emergency Action Levels (EALs). These can be combinations of specific instrument readings (including their rates of change), annunciator warnings, time periods certain conditions exist, etc. The instrument readings and parameters required for determination of these EALs are detailed in the CRN-EPIPs. TVA uses these EALs as thresholds for determining the emergency classifications. The EALs are reviewed annually by the State.
TVA maintains the capability to assess, classify, and declare an emergency condition within 15 minutes after the availability of indication to plant operators that an emergency action level has been exceeded and to promptly declare the emergency condition upon identification of the appropriate EAL.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 5.0 EMERGENCY NOTIFICATION AND ACTIVATION OF PLAN Emergency measures are developed to aid in the mitigation of emergency conditions.
Emergency measures begin with the declaration of an emergency class and activation of associated emergency organizations. These measures, which will include actions for assessment, correction, and protection, are described in general terms for each emergency class in the following parts of this section. Details of these emergency measures will be found in the appropriate sections of the CRN-EPIPs.
When the Plan is activated, TVA initiates certain predetermined actions. Notification is carried out as shown in Figure 5-1 to alert emergency staff personnel to handle the emergency situation.
5.1 ONSITE Upon detection of a known or suspected emergency, the SM on-duty will utilize a CRN-EPIP to determine the classification of the emergency. After determining the classification of the emergency, the SED will initiate the appropriate procedures referenced by the CRN-EPIP. Each procedure referenced by the CRN-EPIP gives specific instructions on staffing the TSC and the OSC and for notifying appropriate State authorities, the ODS, and the NRC.
5.2 OFFSITE Implementing procedures are provided to activate TVA and State emergency staffs. Essential emergency positions are covered on a 24-hour-a-day basis by duty personnel. Emergency response facilities are located to ensure rapid and effective response of personnel needed to assess and evaluate offsite conditions.
5.2.1 NOUE Upon declaration of this classification, TVA initiates the following actions:
A. The Control Room notifies and relays the information to the State within 15 minutes of declaration of the event. TVA utilizes a dedicated ring-down phone to make this notification. TVA utilizes an available commercial telephone line as a back-up method in the event the dedicated circuit is unavailable.
B. The Control Room notifies the NRC immediately after notifying the State but not later than one hour after the emergency declaration is made.
C. The ODS in Chattanooga is notified of the event by the Control Room and records the details of the event in accordance with the appropriate EPIP.
D. The ODS notifies and relays the information to the EDO and CECC Director.
E. The EDO keeps the CECC Director and the Public Information Manager informed of the situation as necessary.
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F. The Public Information Manager notifies the Site Communications Consultant, Director, Public Relations & Corporate Information, and the TVA News Bureau (Knoxville).
G. The SED augments plant on-shift personnel as necessary to initiate corrective or protective actions.
5.2.2 Alert Upon declaration of this classification, TVA initiates the following actions:
A. Notifications outlined in Subsection 5.2.1 are performed.
B. The CECC is staffed.
C. Environmental sampling teams may be dispatched.
D. The TSC and the OSC are activated.
E. The situation is analyzed and any appropriate corrective or preventive actions are initiated.
F. Hourly, or more often as necessary, the State agencies are updated through the CECC on appropriate plant status and environmental conditions as follows:
- 1. Classification of emergency.
- 2. Type of actual or projected release (airborne, waterborne, or surface spill) and estimated duration/impact times.
- 3. Estimate of quantity of radioactive material released or being released and the height of release.
- 4. Chemical and physical form of released material, including estimates of the relative quantities and concentration of noble gases, iodines, and particulates.
- 5. Prevailing weather (wind velocity, direction, temperature, atmospheric stability data, and form of precipitation, if any).
- 6. Actual or projected doses at site boundary.
- 7. Projected dose rates and integrated dose at about 0.5, 1, and 2 miles.
- 8. Estimate of any surface spill radioactive contamination.
- 9. Emergency response actions underway.
- 10. Request for any needed onsite support by offsite organizations.
- 11. Prognosis for worsening or termination of event based on plant information.
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G. The JIC may be activated.
H. Periodic media releases are provided.
I. The SED augments plant on-shift personnel, as necessary, to initiate corrective and protective actions.
5.2.3 Site Area Emergency Upon declaration of this classification:
A. Each of the actions outlined in Subsection 5.2.2 are performed.
B. Personnel knowledgeable of plant systems are dispatched to the SEOC.
C. The CECC recommends appropriate protective actions for the public to State agencies.
D. The JIC is activated.
5.2.4 General Emergency Upon declaration of this classification:
A. Each of the actions outlined in Subsection 5.2.3 are performed.
B. Appropriate PARs to the State are required upon declaration of General Emergency.
C. If this is the initial classification, the Control Room notifies the local government agencies within 15 minutes and provides the PARs.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Site Emergency Director (Control Room)
Operations Nuclear State / Local Duty Regulatory Government(s)1 Specialist Commission Public Emergency Emergency Information Management Duty Officer Manager Organization 1
The Control Room also notifies the local government(s) if the initial classification is a General Emergency.
Figure 5-1 Chains of Notification 22 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 6.0 COMMUNICATIONS The radiological emergency communications network consists of the EP telephone system, the EP notification system, and the EP radio system. These systems are designed to complement each other in the overall plan for REP communications.
The communications facilities described in the following sections are integrated with the requirements for communications to local and State response organizations. TVA conducts testing of these systems in accordance with established procedures.
6.1 EP TELEPHONE SYSTEM The EP telephone system includes communications equipment installed at the CRN site and the CECC, a number of leased commercial circuits, and privately-owned circuits connecting the CRN Site to the required locations.
6.2 PLANT TELEPHONE SWITCHING EQUIPMENT The telephone switching equipment installed at the CRN Site consists of one or more switching centers equipped with fully redundant common logic and redundant power sources. The majority of plant telecommunications services are served from this switching equipment.
6.3 PLANT OR BUILDING LOUDSPEAKER PAGING This system(s) may be accessed from the plant telephone system and is used for normal plant operations (plant paging) and to instruct and notify personnel during an emergency.
6.4 OFFSITE TELEPHONE COMMUNICATIONS The offsite communications network is used to communicate with federal, State, and other supporting agencies. Access to these agencies is provided through several redundant, diverse routes. This diversity provides offsite routing through more than one type of facility. These facilities include, but are not limited to, commercial facilities such as central office trunks, tie-lines and digital services, plus privately owned and maintained microwave and fiber-optic systems. The offsite telecommunications network is designed to facilitate traffic in the most fail-safe manner to the emergency response organizations.
Telecommunications services are provided between the following locations in a redundant, diverse manner:
- CECC to State Emergency Management Agencies.
- CECC to the CRN Site.
- State Emergency Management Agencies to County Emergency Management Agencies.
In addition to the above listed emergency organizations, the following emergency response facilities are also equipped with public telephone lines:
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
- JIC(s).
- Field Coordination Center(s).
ENS and HPN (NRC FTS 2000 System) telephones provide communications from the TSC, Control Room, and the CECC to the NRC Headquarters and regional offices. TVA performs testing of these telephones on a monthly basis.
6.5 EP NOTIFICATION SYSTEM The EP notification system is an automated system which is used to notify key personnel during nuclear emergencies. The EP notification system has provisions to periodically monitor its own performance to detect and report equipment failures.
6.6 TVA ENTERPRISE EMERGENCY NOTIFICATION SYSTEM The TVA Enterprise Emergency Notification System (TEENS) is a hosted Emergency Management Organization notification system that notifies Emergency Management Organization personnel by contacting devices such as assigned office, mobile, and home telephones, work e-mail, and assigned pagers.
6.7 EP RADIO SYSTEM The EP radio system is a VHF mobile radio system which provides redundant radio coverage of the PEP EPZ. It provides radiological monitoring vehicles with mobile communications to other vehicles and to the following locations:
- Radiation Protection.
- TSC.
- Control Room.
- CECC in Chattanooga.
6.8 OTHER RADIO COMMUNICATIONS There is an in-plant repeater system utilized by Nuclear Security Services which enables transmission without interruption to various areas of the plant. A separate radio located in the plant Central Alarm Station (CAS) is a direct link to the local law enforcement agency (LLEA) officials. The plant ambulance has a radio used for communication with the local hospitals and the plant. Portable two-way radios are available for additional site communications.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 7.0 PUBLIC INFORMATION AND EDUCATION 7.1 PURPOSE The purpose of the TVA emergency public information and education program is to ensure timely distribution of accurate information during an emergency in accordance with one or more applicable EPIPs. The program also provides education to the public located within the PEP EPZ on emergency plans. The program also provides for TVA to coordinate emergency information with non-TVA agencies that have a primary response role prior to its release to the public or news media. The program provides for a JIC to be established for use during an emergency. The purpose of the JIC is to provide a single location for TVA, local, State, and federal agencies to coordinate public information activities. On an annual, non-emergency basis, the program provides that TVA, in coordination with the State, disseminates information to the public located within the PEP EPZ regarding emergency notification methods and actions.
In addition, TVA and the State conduct coordinated annual orientations to acquaint the local area news media with the emergency plans, radiological information, and points of contact for release of information in an emergency.
7.2 RESPONSIBILITIES 7.2.1 CECC Director The CECC Director or delegate is responsible for approving written news statements after the CECC is activated.
7.2.2 JIC Spokesperson The JIC Spokesperson is responsible for representing TVA during news briefings and coordinating information with other federal, State, and local spokespersons prior to the briefings.
7.2.3 Director, Public Relations & Corporate Information Director, Public Relations & Corporate Information is responsible for directing emergency public information activities of the agency in accordance with approved procedures. This includes the responsibility for coordinating with the CECC Director and non-TVA agencies, who would participate in JIC activities, in determining when to activate or deactivate the JIC.
7.2.4 Operations Communications Operations Communications is responsible for the development, implementation, and maintenance of nuclear public information organizations and activities for an emergency, as well as those nuclear public information programs conducted on an annual basis.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 7.3 PUBLIC INFORMATION FACILITIES Public Information personnel are present at three locations with sufficient staff available to maintain operations on a 24-hour basis: (1) Operations Communications directs the activities of the emergency public news media present at the site; (2) the CECC in the Chattanooga Office Complex where staff will develop news releases and coordinate the news releases with offsite agencies; and (3) the JIC where staff coordinates with the offsite agencies in presenting emergency news briefings and respond to public telephone inquiries.
7.4 COORDINATION OF INFORMATION Prior to activation of the CECC, coordination of public information with non-TVA primary response agencies is handled through Operations Communications in accordance with emergency public information procedures. Upon activation and staffing of the CECC, the responsibility for coordination of public information with non-TVA agencies shifts to the CECC Information Staff. Upon activation and staffing of the JIC, the responsibility for coordination of public information shifts from the CECC to the JIC emergency response staff when and if offsite agencies are also operational at the JIC. The CECC Director continues to approve written news statements. Non-TVA primary response agencies are provided copies of written news statements until they are available to support coordination in the JIC.
7.5 PUBLIC EDUCATION TVA coordinates development and distribution of public education materials and programs with the appropriate State agency. Distribution of public information on actions the permanent and transient populations should take in the event of an emergency occurs annually. Mailing lists for the public in the PEP EPZ are updated annually to assure thorough and accurate distribution of the emergency information.
7.6 EMPLOYEE COMMUNICATIONS An information system that employees can access provides a method of informing TVA employees who do not have emergency response assignments about an emergency.
7.7 RUMOR CONTROL/PUBLIC INFORMATION Teams in the JIC are responsible for emergency information. In the JIC, a trained media relations team responds to news media inquiries by telephone and media briefing and a trained information team responds to citizen telephone inquiries. Also in the JIC, a trained media monitoring team monitors news media coverage. TVA coordinates information activities with offsite agencies at the JIC.
7.8 TRAINING TVA provides initial training and annual retraining to emergency public information staff to allow them to respond.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 8.0 EMERGENCY RESPONSE FACILITIES, EQUIPMENT, AND SUPPLIES 8.1 NUCLEAR SITE FACILITIES 8.1.1 Technical Support Center The CRN Site has a Technical Support Center (TSC) which is dedicated for use during an emergency. Once activated, the TSC is the focal point of onsite activity and is the primary source of communication from the site with offsite organizations during the event. The TSC has sufficient staff to provide management control of the site response to the event. Equipment is available to enable the TSC staff to communicate with onsite and offsite TVA emergency personnel. An area within the TSC is dedicated for NRC use which includes commercial telephones and the NRC FTS 2000 System telephones. Sufficient plant parameter information is available to the TSC to enable the TSC staff to assess the consequences of an event and assist the Control Room personnel in mitigating the emergency. Sufficient information is transmitted to the CECC to enable the CECC Director to make PARs to State authorities.
The TSC is activated during radiological emergencies in accordance with CRN-EPIPs. The degree of activation varies depending upon the emergency class. Additional information regarding the TSC is provided in Appendix A.
8.1.2 Operations Support Center The CRN Site has an Operations Support Center (OSC) which is a pre-designated area for the assembly of personnel to support the Control Room Operations crew during an emergency. The OSC area(s) is under the control of the SED in the Control Room until the TSC is staffed and will provide damage assessment, maintenance and repair services, and necessary technical services. Communications are available with the TSC. The OSC also establishes and maintains appropriate communications with any teams that may enter the plant for assessment or repair.
Respiratory protective devices, protective clothing, portable lighting, other protective equipment and tools are available in the OSC, as needed.
The OSC is activated during radiological emergencies in accordance with CRN-EPIPs. The degree of activation varies depending upon the emergency class. Additional information regarding the OSC is provided in Appendix A.
8.1.3 Local Recovery Center The CRN Site has a Local Recovery Center (LRC) which is a pre-designated facility dedicated for use by offsite TVA and NRC personnel that may be assigned to the CRN Site for recovery operations. In addition, the LRC may be used by the NRC during the event as an area near the site for assessment and assistance and has the capability to communicate offsite. Personnel in the LRC have access to necessary drawings and documents. Meteorological information is available in the LRC. The LRC may serve as an alternate emergency response facility, as needed, and during an emergency, may be used as a staging location for personnel prior to dispatch to the CRN Site. Additional information regarding the LRC is provided in Appendix A.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 8.1.4 Site Decontamination Facilities The CRN Site has facilities for the decontamination of personnel including those with injuries.
Information on these facilities is provided in Appendix A.
8.1.5 Equipment, Supplies, and Supplemental Data The CRN Site has sufficient equipment and supplies for the operation of the site emergency response facilities. Additional seismic and hydrological information can be obtained by the CECC from other TVA nuclear plants or the TVA water quality organization. Reference Appendix A, Attachment 2 for additional information regarding emergency equipment and supplies.
8.2 CENTRAL EMERGENCY CONTROL CENTER The purpose of the Central Emergency Control Center (CECC) and associated CECC staff is to provide the facilities and manpower for evaluating, coordinating, and directing the overall activities involved in coping with a radiological emergency. The specific response time for staffing the CECC will be determined as a result of evaluating the specific accident sequences and included in the COLA.
During an emergency, the CECC Director and staff will review the response to the emergency by TVA and the appropriate State agencies to ensure that an effective and cooperative effort is being made. The CECC Director is responsible for providing PARs to the appropriate State officials.
The CECC staff coordinates with other TVA emergency response facilities to ensure an effective TVA effort in response to an emergency situation. The CECC staff also provides an accurate description of the emergency situation for TVA management and public information. In addition, the CECC coordinates with offsite federal agencies, such as NRC and DOE, to ensure availability of additional outside resources to TVA.
The CECC is located in the northeast corner of the sixth floor of Lookout Place in the TVA Chattanooga Office Complex (COC) in Chattanooga, Tennessee. It is designed to house the CECC Director and staff during an emergency situation. Included in the CECC are areas for the Plant Systems Assessment, Radiological Assessment, and Public Information Staff. A floor plan for the CECC is provided in Figure 8-1. Access control to the CECC is provided by Security personnel.
The CECC is designed to serve as the central point for information collection, assessment, and transfer during an emergency. The CECC is provided with direct communication links with State emergency response centers, other TVA emergency response organizations, other TVA nuclear plant sites, the JIC, and offsite federal and State organizations.
The CECC is activated during radiological emergencies in accordance with CRN-EPIPs. The degree of activation varies depending upon the emergency classification. of this Plan provides additional description of and justification for the location of the CECC.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 8.3 RADIOLOGICAL MONITORING CONTROL CENTER The Radiological Monitoring Control Center (RMCC) is located in the Tennessee Emergency Management Agency East facility (TEMA East) in Knoxville, Tennessee, and is staffed by the TVA Field Coordinator and personnel from the State. These personnel cooperate in providing direction and control of the monitoring teams.
Monitoring teams have maps of the area and are directed to selected monitoring points or locations to collect data. This data is transmitted to the RMCC and CECC for analysis.
Facilities at the RMCC include radio and telephone communications, and necessary desks, tables, and chairs. Maps of the PEP EPZ and the ingestion exposure pathway EPZ are located at the RMCC.
8.4 JOINT INFORMATION CENTER The CRN Site has a Joint Information Center (JIC) established near the site to assist the news media in providing press coverage during an emergency. The location, function, and capabilities of the JIC is addressed in the CRN Site COLA.
8.5 ALERT AND NOTIFICATION SYSTEM Information regarding the CRN Site Alert and Notification System (ANS) is provided in Appendix A. Additional details describing the CRN Site ANS will be addressed in the CRN Site COLA.
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Clinch Riiver Nuclea ar Site Early Site Permit P App lication Partt 5B, Emergency Plan ((2-Mile EPZZ)
Figure 8-1 Central Emergency E y Control C Center 30 Revission 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 9.0 ACCIDENT ASSESSMENT 9.1 ONSITE In-plant accident assessment actions are carried out by the plant emergency staff in order to properly characterize and classify the emergency, determine the actual or potential radioactivity releases, and determine the effect on plant personnel and the public.
Assessment methodology consists of actions carried out through plant operating procedures as well as CRN-EPIPs. At the onset of an emergency, plant operating procedures (normal, abnormal, and emergency) assist the plant operator and SED in identifying the cause of the emergency, actions necessary to control the emergency, radioactivity release rate, if any, and in-plant radiation levels. The CRN-EPIPs assist the SED in: (1) identifying and reassessing emergency classification; (2) determining the need for offsite protective actions; (3) determining the need for plant area evacuation; (4) initiating activation of onsite and offsite emergency organizations; (5) directing the utilization of needed medical and/or decontamination facilities; and (6) implementing predetermined security and access control plans.
Each of the above-mentioned activities is described within the plant operating procedures or CRN-EPIPs, as applicable, for a given situation. The distinct breakdown of assessment actions into operating procedures and implementing procedures is necessary since some assessment actions are necessarily carried out prior to identification or classification of an emergency. The procedures to ensure that emergencies are properly evaluated, timely notifications are made, and assessment and protective actions are performed, are compiled in the CRN-EPIPs. These procedures are summarized by topic in Appendix A, Attachment 1.
Under severe emergency conditions, and as required by the plant emergency operating procedures, the onsite Emergency Management Organization is responsible for recognition of severe emergency conditions, transition to, and implementation of the Severe Accident Management Guidelines (SAMGs).
9.2 OFFSITE 9.2.1 General Information TVA and State agencies are prepared to assess the consequences of potential or actual releases of radioactivity offsite. State and local agencies implement protective actions for the public. Written messages have been prepared which give the public instructions with regard to specific protective actions to be taken by occupants of affected areas. These messages are included in the State Plan referenced in Appendix A, Attachment 1.
Implementing procedures have been developed for the CECC to ensure that emergencies are properly evaluated, timely notifications are made, and assessment and protective actions are performed. Once an SMR technology is selected, the details on staffing levels, response times, and accident progression rates will be known and can then be reflected in a set of EPIPs similar to the following list:
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- CECC-EPIP-1-CENTRAL EMERGENCY CONTROL CENTER OPERATIONS
- CECC-EPIP-2-OPERATIONS DUTY SPECIALIST PROCEDURE FOR NOTIFICATION OF UNUSUAL EVENT
- CECC-EPIP OPERATIONS DUTY SPECIALIST PROCEDURE FOR ALERT, SITE AREA EMERGENCY, OR GENERAL EMERGENCY
- CECC-EPIP-4-NOT ACTIVE AT THIS TIME
- CECC-EPIP-5-NOT ACTIVE AT THIS TIME
- CECC-EPIP CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY
- CECC-EPIP CECC RADIOLOGICAL ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY
- CECC-EPIP DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES
- CECC-EPIP-9-EMERGENCY ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURES
- CECC-EPIP-10-NOT ACTIVE AT THIS TIME
- CECC-EPIP-11-SECURITY OF OFFSITE EMERGENCY RESPONSE FACILITIES
- CECC-EPIP-12-OPERATIONAL READINESS CHECK OF THE CECC AND THE FIELD COORDINATION CENTERS FOR SQN, BFN, WBN & CRN AND JOINT INFORMATION CENTERS (JIC)
- CECC-EPIP-13-NOT ACTIVE AT THIS TIME
- CECC-EPIP-14-NUCLEAR EMERGENCY PUBLIC INFORMATION ORGANIZATION AND OPERATIONS
- CECC-EPIP EP FIELD SUPPORT STAFF RADIOLOGICAL EMERGENCY PROCEDURE
- CECC-EPIP TERMINATION AND RECOVERY
- CECC-EPIP CENTRAL EMERGENCY CONTROL CENTER METEOROLOGIST PROCEDURES
- CECC-EPIP-18-TRANSPORTATION AND STAFFING UNDER ABNORMAL CONDITIONS 32 Revision 1
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- CECC-EPIP POST EMERGENCY FUEL DAMAGE ASSESSMENT
- CECC-EPIP NOT ACTIVE AT THIS TIME
- CECC-EPIP EMERGENCY DUTY OFFICER PROCEDURE FOR NOTIFICATION OF UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY
- CECC-EPIP OPERATIONS DUTY SPECIALIST TRANSPORTATION INCIDENTS INVOLVING A SHIPMENT OF RADIOACTIVE MATERIAL
- CECC-EPIP RADIOACTIVE MATERIAL TRANSPORTATION INCIDENTS 9.2.2 Sampling Team TVA has vehicles equipped to monitor the environment for radioactivity. Each vehicle has an air sampler, radiation measurement equipment, a generator, radio, and other assorted equipment.
A detailed listing of the minimum required equipment is available in the CECC-EPIPs.
These vehicles are dispatched for environmental monitoring for Site Area Emergency and General Emergency classifications. TVA may deploy these vehicles for the NOUE and Alert classifications, if warranted. One or more vehicles is stationed at the CRN Site.
Each sampling team has the capability to:
- Obtain environmental samples for analysis.
- Make direct radiation readings.
- Collect air samples and analyze them for gross beta-gamma radioactivity over a range of energies.
- Collect air samples and analyze them for radioiodine in the field, to concentrations as low as 10-7 microcuries/cc.
CRN-EPIPs describe the composition and activation of sampling teams.
For the Site Area Emergency and General Emergency classifications, teams are dispatched from the nearest location. Teams may be deployed for the NOUE or Alert, if warranted. If necessary, TVA can coordinate team transport via helicopter or fixed-wing aircraft.
The TSC Rad Protection Manager or CECC Environs Assessor can request assistance from a neighboring plant for environmental monitoring, if deemed necessary.
TVA has aquatic monitoring teams located at Chattanooga, Tennessee, and Knoxville, Tennessee. These teams have boats that can be deployed to obtain samples from the river for subsequent analysis for radioactivity in the laboratories.
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State agencies have the responsibility to coordinate and evaluate offsite assessment actions.
Environmental monitoring activities are coordinated through the RMCC. State environmental monitoring capabilities and the RMCC operations are referenced in Appendix A, Attachment 1.
TVA personnel are co-located in the RMCC, which provides for coordination of TVA and State monitoring teams. TVA and the State share environmental monitoring data.
Additional environmental monitoring assistance is available from the DOE offices at Oak Ridge, Tennessee, or Aiken, South Carolina. The EPA in Montgomery, Alabama, can also provide assistance. Available support includes environmental monitoring teams and mobile radioanalytical laboratories. The State agencies usually request and coordinate these services.
9.2.3 Analyzing Environmental Samples The sampling teams may send samples to the WARL for analysis. The WARL has the capability to perform further quantitative and qualitative analysis. The WARL is available as needed and can be operated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. The WARL can establish a central point for receipt of samples when needed.
9.2.4 Meteorological Information 9.2.4.1 Primary Meteorological Measurements TVA has developed the meteorological measurements program to conform to the intent and guidance of Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants (RG 1.23). Wind direction, wind speed, and air temperature are measured at two levels.
The temperature difference is used to estimate the Pasquill stability class. Precipitation and dew point temperature are also measured. Hourly and 15-minute average meteorological data from the plant Environmental Data Station are available to the CECC, TSC, State, and LRC. More specific information on the meteorological measurements program can be found in Section 2.3 of the CRN SSAR.
9.2.4.2 Backup Meteorological Data Estimation Procedures TVA has prepared objective backup procedures to provide estimates for missing or garbled data needed to perform dose calculations and to determine transport estimates. They incorporate available onsite and offsite data. Each procedure has an accompanying statement of reliability.
9.2.4.3 Real Time and Forecast Meteorological Data The CECC Meteorologist has the responsibility for providing meteorological information to CECC Staff. The dose assessors use this meteorological information to project offsite doses.
Plume positions are plotted on a site area map. The meteorological support actions and projection of doses are discussed in detail in CECC-EPIPs. Meteorological support may be provided in the CECC or from a remote location.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 9.2.4.4 Remote Access of Meteorological Data Access of up to the most recent 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of 15-minute and hourly meteorological data is available to authorized users through the CECC computer. The remote access system gathers data from the CRN Site, performs unit conversion, reformats data, and flags questionable values.
9.2.5 Dose Assessment On-shift dose assessment capability is maintained at the CRN Site, and can be implemented (if needed during the initial phase of an emergency) until the CECC is activated and assumes the dose assessment function.
Offsite doses from emergency-related releases of radioactivity are estimated using a combination of calculations, field measurements, and laboratory analyses of environmental samples. Data on meteorological conditions are used in determining offsite dispersion factors.
Using plant operational data, field measurements, and effluent monitor readings, actual or potential releases of radioactivity are analyzed by the plant staff, the Radiological Assessment staff, or the CECC Plant Assessment Team to generate or modify a source term for use in the dose assessment.
With this information, the CECC dose assessment team can predict offsite doses through the use of several models and/or methods described in the CECC-EPIPs. These models provide a means of estimating public exposures throughout the emergency and recovery period. Environs measurements are used, to the extent possible, to confirm doses projected by modeling.
A preliminary dose projection is performed following receipt of measured effluent release data (the source term) and meteorological data. The preliminary dose projection is followed up by a more detailed assessment using computerized dose models. Manual dose assessment methods are available for use in the event that the computer is unavailable. Input to the detailed calculations includes measured source terms, projected future releases, near real-time and forecast meteorological data, field measurements of exposure rates and/or airborne radioactivity in the environs around the plant, or a combination thereof. Field measurements are used to estimate doses, and (especially in the case of an unmonitored release) source terms, and to verify doses projected using models.
After termination of emergency-related releases to the atmosphere, integrated doses are calculated to assist in recovery/reentry operations. A combination of inputs including results from modeling field exposure rate and air concentration measurements and laboratory analyses of soil, vegetation, and water samples are used to assess doses. Recommendations are made regarding evacuation area clearance and reentry based on doses calculated for exposure from ground contamination, inhalation of re-suspended radioactivity, and ingestion of radioactivity in vegetables and milk.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 10.0 PROTECTIVE RESPONSE 10.1 ONSITE PROTECTIVE ACTIONS FOR RADIOLOGICAL EVENTS In the event of an unplanned significant release of radioactivity or sudden increase in radiation levels, it is the responsibility of the SED to make the decision concerning the necessity for building and area evacuation. In arriving at this decision, the primary consideration is personnel safety. The SED may use the various radiation and airborne radioactivity monitors placed throughout the plant, with readout in the Control Room, to assess the extent of the radiological hazards and to determine the extent of evacuation necessary.
The assembly/accountability alarm is used to initiate the assembly of site personnel. The public address system is used if only specific areas are to be evacuated. Nuclear Security Services personnel patrol the area between the security boundary described in the Physical Security Plan and the Site Boundary, and evacuate any nonessential personnel.
Upon hearing the emergency alarm, persons in the plant areas proceed to their pre-assigned areas to be accounted for and await further instructions from the SED. The pre-assigned areas are designated in approved procedures. Predetermined assembly areas are identified in approved procedures and radiological surveys are completed as required by the TSC. The number of unaccounted individuals should be available within approximately 30 minutes for persons within the security area as defined in the Physical Security Plan.
If only a particular area is cleared, personnel in that area evacuate to a safe area. An accountability report is provided to the SED from Security. Further details of evacuation procedures are described in CRN-EPIPs.
If radiation levels or airborne radioactivity at an assembly point is significantly higher than alternative assemble areas, or the SED deems it necessary, the SED orders relocation to a safe assembly point. Employees are released from this assembly point when the SED determines it is suitable to do so.
Procedures require that potentially contaminated people and vehicles pass through a Rad Protection check-point for survey prior to being released.
In the event of the evacuation of nonessential site personnel, the SED notifies the CECC Director. If the personnel require transportation and sheltering, the CECC Director coordinates arrangements with the appropriate State agency. If the evacuees require radiological decontamination, they are informed of transportation, sheltering, and decontamination arrangements prior to leaving the plant site. An alternate decontamination facility is specified in a CRN-EPIP.
Contaminated personnel are decontaminated to the limits specified in the CRN Site Radiological Control Instructions (RCIs) by methods described in the instructions before being released by TVA.
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Procedures also specify the action to be taken by, and the accountability of, personnel having an emergency assignment. Essential plant personnel remaining onsite are protected by plant systems designed to provide a habitable environment even under the most serious emergency conditions or by precautionary measures such as the use of respiratory protective equipment and protective clothing. Personnel doses are controlled in accordance with Section 11.0.
10.2 ONSITE PROTECTIVE ACTIONS FOR HOSTILE ACTION EVENTS A range of protective actions to protect onsite personnel during a Hostile Action event are developed to ensure the continued ability to safely shut down the reactor(s) and perform the functions of the Emergency Plan. This range of protective actions are contained in the CRN Site abnormal procedures. These procedures are classified security sensitive.
10.3 OFFSITE Should an event be initially classified as a General Emergency, the SED has the responsibility to determine an initial protective action for recommendation to State and local government agencies. CRN-EPIPs provide a logic diagram as a decisional aid to facilitate this recommendation.
After the CECC is staffed, the responsibility for PARs is transferred to the CECC Director. The CECC Plant Assessment Manager provides an assessment of actual and projected plant conditions. The RAM provides an assessment of actual and/or projected radiological conditions offsite. The RAM also provides a recommendation for a specific protective action. The CECC Director evaluates the recommendation from staff and make a recommendation to the State.
The logic diagram for PEP recommendations is provided in the CECC-EPIPs as a decisional aid to facilitate the recommendation.
The State and local agencies are responsible for implementing actions to protect the health and safety of the public offsite. Although TVA may recommend protective actions to these agencies, the State and local governments are responsible for deciding if any actions are needed and what they should be. The CECC will discuss and provide ingestion exposure pathway recommendations (i.e., agricultural) and recommendations for liquid releases (i.e., closing of public water supplies) with the State as appropriate.
The decision to implement one or more of the above actions is based upon some or all of the following considerations:
- Projected offsite integrated doses.
- Actual measured dose rates.
- Present and future weather conditions.
- Projected improvement or deterioration of plant conditions.
- State protective action guides.
- Levels of airborne radioactivity.
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- Levels of waterborne radioactivity.
- Concentrations of radioactivity in items for human consumption.
- Evacuation time estimates (from Evacuation Time Estimate or maintained in the State Plan).
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 11.0 RADIOLOGICAL PROTECTION The Radiological Protection Section at the CRN Site is responsible for Radiological Protection activities onsite. Its function is to develop instructions to implement the requirements of Title 10 Code of Federal Regulations, Part 20, and other required standards as well as the requirements and policies in TVA radiological control procedures. The Section provides surveillance during normal operation as well as emergency situations. In addition, the Section advises key plant personnel on radiological matters for routine and emergency conditions.
The limiting doses to occupational workers during routine plant operations are found in TVA radiological control procedures. If possible, TVA maintains these limits during emergency operations. If these standards cannot be met during emergencies, TVA implements the dose guidance described in Table 11-1. A CRN-EPIP describes the methods to use and authorizes the doses outlined in Table 11-1. Table 11-2 describes the health effects of radiation doses greater than 25 RAD.
For individuals entering radiation work permit areas, electronic dosimeters and primary dosimeters are issued and read in accordance with the site TVA radiological control procedures.
The electronic dosimeters can be read at any time. Primary dosimetry processing and evaluation is performed by an organization currently accredited by the National Voluntary Laboratory Accreditation Program (NVLAP) of the National Institute of Standards and Technology for the type or types of radiation that most closely approximates the type of radiation or radiations for which the individual wearing the dosimeter is monitored. Dose records are maintained on each monitored individual by a computer.
TVA radiological control procedures contain the criteria used to establish contamination zones and to release personnel, equipment, and clothing. Onsite facilities are available to decontaminate equipment and personnel.
Procedures for using individual respiratory protection and protective clothing are provided in specific plant operating procedures. Procedures for the use of radioprotective drugs are provided in the EPIPs. Drinking water and eating controls are established by Radiation Protection.
Authorizations for emergency dose limits for onsite personnel is provided by the SED while authorizations for offsite personnel is provided by the CECC Radiological Assessment Manager.
TVA implements adequate protective measures so that dose, considering both internal and external pathways, is maintained As Low As Reasonably Achievable (ALARA). Internal dose is minimized by the use of respiratory protection equipment consistent with maintaining the Total Effective Dose Equivalent (TEDE) ALARA, and protective clothing is used to minimize personnel contamination. If a projected dose to a workers thyroid is expected to exceed 10 rem during a radiological emergency, Potassium Iodide (KI) is issued in accordance with applicable implementing procedures.
Personnel shall not enter any area where dose rates are unknown or unmeasurable with either instruments or available dosimetry.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Receipt of emergency exposures in excess of 10 CFR 20.1201 limits shall be on a voluntary basis. Personnel receiving emergency exposures shall be informed of the risks involved including the numerical levels of dose at which acute effects of radiation will be incurred, and numerical estimates of the risk of delayed effects. Table 11-2 provides information consistent with Environmental Protection Agency Protective Action Guides and Planning Guidance for Radiological Incidents (EPA PAG Manual), Draft for Interim Use and Public Comment, dated March 2013," which may be useful for this briefing purpose.
Personnel receiving emergency doses should be restricted from further occupational exposure pending the outcome of exposure evaluations, and, if necessary, medical surveillance.
Any personnel dose in excess of five (5) rem TEDE shall be handled in accordance with the TVA Nuclear Radiological Protection Plan.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
TABLE 11-1 EMERGENCY WORKER DOSE GUIDANCE TEDE Dose Condition 5 rem All, maintain dose ALARA 10 rem Protection of valuable property when lower dose not practicable.
25 rem Lifesaving or protection of large populations when lower dose not practicable.
Greater than 25 rem Lifesaving or protection of large populations when lower dose not practicable.
Only on a volunteer basis to persons fully aware of the risks involved.
NOTE: Situations may occur in which a dose in excess of regulatory limits (10 CFR 20.1201) would be required for plant and lifesaving operations. It is not possible to prejudge the risk that one person should be allowed to take in these situations. However, persons undertaking an emergency mission in which the dose would exceed regulatory limits should do so only on a voluntary basis and with full awareness of the risks involved (EPA PAG Manual, March 2013).
Guidance for dose to the lens of the eye is three (3) times the listed TEDE value. Dose to any other organ (including skin and body extremities) is ten (10) times the listed TEDE value.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
TABLE 11-2 HEALTH EFFECTS OF RADIATION DOSES GREATER THAN 25 RAD I. Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours1.
Whole Body Early Whole Body Prodromal Absorbed Dose Fatalities2 Absorbed Dose Effects3 (rad) (percent) (rad) (percent) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 1
Risks will be lower for protracted exposure periods.
2 Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.
3 Forewarning symptoms of more serious health effects associated with large doses of radiation.
II. Approximate Cancer Risk to Average Individuals from 25 Rem Effective Dose Equivalent Delivered Promptly.
Risk of Premature Death Average year of life Age at Exposure (deaths per 1,000 persons lost if premature death (years) exposed) occurs (years) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11 Note: Tables referenced from the "Environmental Protection Agency Protective Action Guides and Planning Guidance for Radiological Incidents (EPA PAG Manual), Draft for Interim Use and Public Comment, dated March 2013."
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 12.0 MEDICAL SUPPORT 12.1 GENERAL INFORMATION Facilities, equipment, medical supplies, and trained personnel are available for first aid/emergency medical treatment of ill or injured persons onsite.
Guidance for medical assistance is found in a CRN-EPIP. Immediate lifesaving and disability limiting procedures take precedence over noncritical decontamination and dosimetry assessment measures.
When activated, the CECC coordinates the care, disposition, and reporting of injuries known or suspected to be associated with excess levels of radiation exposure or contamination. The purpose of the Medical Emergency Response Team (MERT) (team composition specified in a CRN Site procedure) is to:
- Provide first aid/emergency medical treatment for ill or injured persons onsite, including those who may have been exposed to or contaminated with radioactive material.
- Minimize injury during the rescue, treatment, and transport of injured persons, while minimizing radiological hazards and exposure to the victim.
- Advise and protect attending personnel from unacceptable and unnecessary radiological hazards and exposures.
- Identify, document, and control radiation exposure and contamination hazards associated with the emergency.
12.2 CLASSIFICATION AND HANDLING OF MEDICAL EMERGENCY PATIENTS 12.2.1 Noncontaminated-Nonirradiated When it is known that the patient is not contaminated and has not been overexposed to radiation, TVA handles the patient according to standard first aid/emergency medical protocol.
The patient, ambulance crew, receiving hospital, and attending physician (as applicable) are advised of the absence of radiological complications.
12.2.2 Irradiated-Noncontaminated TVA coordinates the removal of the patient from the source of radiation exposure as soon as medical conditions and essential treatments permit. Continued medical care for physical injuries, including ambulance transport, is provided as indicated. Rad Protection determines and reports radiation exposure levels, including affected body areas. Emergency care for the radiation exposure is governed by the dose assessment and the medical status. Involved personnel are advised of the absence of radiological contamination.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 12.2.3 Contaminated For patients known to be or suspected of being contaminated, TVA coordinates essential first aid and emergency medical care. Decontamination activities are accomplished as the medical status permits. Involved personnel are advised of the contamination hazard. Continued care and decontamination decisions are made on an individual basis by the responsible medical care provider and Rad Protection.
12.3 TRANSPORTATION OF INJURED PERSONNEL The decision to transport a patient offsite is the responsibility of the emergency medical care provider performing patient assessment, i.e., Emergency Medical Technician (EMT) or Registered Nurse. If conflicting decisions arise, the option which provides the patient with the optimal level of medical care is chosen.
When ambulance transportation is indicated, transport may be provided by either the site Fire Protection EMTs (using a TVA ambulance) or by an agreement ambulance service. The MERT Team Leader coordinates requests for offsite ambulance assistance through the SM. The SM performs initial requests and notifications for assistance.
TVA maintains arrangements for one or more agreement ambulance services for the CRN Site with trained personnel to transport patients, including those who may have been exposed to or contaminated with radioactive material. These services are designated in a CRN-EPIP and letters of agreement for response are maintained. (See Section 16.5.)
12.4 INTERAGENCY ASSISTANCE FROM REAC/TS TVA maintains arrangements with the Radiation Emergency Assistance Center/Training Site (REAC/TS) as the CRN Site receiving hospital. REAC/TS, which is in close proximity to the CRN Site, is a DOE-sponsored facility operated by Oak Ridge Associated Universities Medical and Health Sciences Division in cooperation with the Oak Ridge Methodist Medical Center in Oak Ridge, Tennessee. The University of Tennessee Medical Center in Knoxville, Tennessee serves as a back-up to REAC/TS. Specialized facilities and expert personnel are available at both medical facilities for definitive care for radiation emergency victims. Letters of Agreement for services are maintained. (See Section 16.5.)
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 13.0 TERMINATION AND RECOVERY 13.1 TERMINATION The SM/SED is responsible for the decision to terminate an event for which the onsite and offsite emergency response facilities have not been activated.
In the event of an incident requiring activation of onsite and offsite emergency centers, the SED coordinates the decision to terminate the event with the CECC Director after consultation with the plant technical and operations staffs. This decision is based upon a comprehensive review of plant status and system parameters. These considerations include, but are not limited to, the following:
- Stability of the reactor shutdown condition, i.e., successful progress toward a cold shutdown condition.
- Integrity of the reactor containment building.
- Operability of engineered safety systems and decontamination facilities.
- Availability and operability of a heat sink.
- Integrity of power supplies and electrical equipment.
- Operability and integrity of instrumentation including radiation monitoring equipment (also including portable equipment assigned during the emergency).
- Availability of trained personnel and support services.
- Control of radiological effluent releases.
State representatives are responsible for decisions to relax protective actions for the public. The CECC Director provides information to the appropriate State agencies to facilitate the decision.
The State has the authority and responsibility for offsite recovery efforts. TVA will provide assistance, as requested, through the recovery organization shown in Figure 13-1. (Figure 13-1 lists functions which must be addressed for recovery; the normal organizational titles may be different than what is represented here.)
The CECC Director, after consultation with the State, the SED, and discussion with the NRC (if appropriate), announces that the emergency has terminated and the recovery phase is to be initiated, if appropriate. TVA then develops procedures and plans to implement the most expeditious recovery sequence to return the plant to normal operation.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Chief Nuclear Officer VP CECC SVP VP VP Nuclear Nuclear SVP Public Engineering Nuclear Licensing Operations Operations Information
& Support Oversight Support Manager Reactor Corporate General Engineering Functional Site Vice Manager,
& Fuels Area President Quality General Manager: Assurance Manager -Rad Protection Senior -Chemistry Manager -Maintenance Plant Equipment -Work Control Manager &
Reliability / -Operations Administrative Systems -ENG/Rad Support Engineering Monitoring Instruments Program Manager -Radwaste &
Senior Mechanical/Nuclear Environmental Manager Engineering Design Protection Design Program Manager Engineering Electrical/I&C Engineering Design Senior Program Nuclear Senior Manager Site Manager Nuclear Security Systems Security Engineering Director Site EP
-Civil/Structural Emergency Manager Engineering Preparedness Director -Electrical/I&C Site Engineering Engineering -Mechanical
/Nuclear Engineering Figure 13-1 TVA Recovery Organization 46 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 13.2 RECOVERY ORGANIZATION 13.2.1 Chief Nuclear Officer The Chief Nuclear Officer will direct the overall recovery effort. If the recovery phase is expected to be a long-term process, he may form a team to be responsible for continuous control of the recovery operation, thus permitting other personnel to return to their normal duties. The organizational structure of such a team would be contingent upon the emergency situation and procedures required for recovery. The LRC is available to provide additional office space near the site for the recovery team at the discretion of the Chief Nuclear Officer.
13.2.2 Senior Vice President Operations The Senior Vice President Operations is responsible for the onsite recovery effort and for developing required recovery procedures. He requests any needed offsite support through the Site Vice President and/or Plant Manager.
13.2.3 Site Vice President The Site Vice President is responsible for coordinating the onsite efforts with the overall TVA recovery effort. The Site Vice President (SVP) is in charge of the LRC should additional office space be needed.
13.2.4 Vice President, Operations Support The Vice President, Operations Support directs that the Corporate Functional Area Managers provide support in the following areas:
- Radiological Protection
- Chemistry
- Maintenance
- Work Control
- Operations
- Radwaste & Environmental Protection
- Nuclear Security Services
- Eng/Rad Monitoring Instrument
- Technical support and Environs sampling assistance as requested by the State
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
- Environmental Monitoring 13.2.5 CECC Public Information Manager The CECC Public Information Manager acts as an interface between TVA and the news media.
Assists the Chief Nuclear Officer in drafting news releases concerning progress of the recovery operation. Coordinates news releases with TVA management and State and federal officials as required. Coordinates press briefings and interviews concerning the incident.
13.2.6 Vice President, Nuclear Licensing The Vice President, Nuclear Licensing provides support in various licensing issues including primary interaction with the NRC.
13.2.7 Vice President, Engineering & Support The Vice President, Engineering & Support provides support in the area of plant components, Reactor Engineering, fuels and in various engineering disciplines.
13.2.8 Vice President, Nuclear Oversight The Vice President, Nuclear Oversight provides Quality Assurance oversight of the recovery process.
13.2.9 Other TVA Resources Other TVA resources plus other governmental and vendor support will be available through the TVA corporate organization to aid the SED in developing, evaluating, and implementing specific site recovery and reentry operations.
13.3 ONSITE RECOVERY Major post-emergency onsite recovery measures are performed in accordance with written procedures. Additional procedures which may be developed following an emergency include the following activities:
- The first auxiliary/reactor building entry.
- The first containment building entry.
- Damage evaluation
- Decontamination
- Disassembly
- Repair
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- Test and startup of restored facilities.
Appropriate personnel protective measures are taken on initial entries and throughout assessment and recovery operations to limit exposures to those outlined in Section 11.0.
Reentry and recovery individual and population dose estimates are obtained using dose rate measurements or calculations and population distribution (see Section 9.2.5). The CECC-EPIPs contain this methodology.
13.4 LOCAL RECOVERY CENTER The LRC provides a facility for TVA recovery management as well as NRC emergency response personnel and other emergency and/or recovery personnel. The LRC provides adequate space for TVA and others who may locate there to support the site should additional office space near the site become necessary during the recovery phase. The LRC provides dedicated space for NRC personnel and contains adequate supplies, communications, and data necessary for them to carry out appropriate functions. See Appendix A for the description of the CRN Site LRC.
13.5 OFFSITE RECOVERY The State has the authority for actions taken offsite; however, TVA serves as an important source of technical and analytic assistance for the State in offsite monitoring and sampling needed to determine the extent and methods of offsite recovery. The Chief Nuclear Officer, or designee, serve as the State's contact for coordination of TVA efforts in offsite monitoring, sampling, and recovery.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 14.0 DRILLS AND EXERCISES 14.1 DRILLS Drills are conducted to develop and maintain key skills required for emergency response. These drills may be conducted individually or as part of an REP exercise.
The following drills are required:
14.1.1 Medical Emergency Drills A medical emergency drill involving a simulated contaminated/injured individual, with participation by a TVA or agreement ambulance and each agreement hospital (see Section 16.5) is conducted each calendar year for the CRN Site. Scenario development, drill activities, and evaluations will be jointly conducted and critiqued by EP and the site.
14.1.2 Radiological Monitoring Drills Environmental monitoring vehicle drills are conducted each calendar year for the CRN Site.
These drills include collection and analyses of sample media (i.e., water, air, grass, and/or soil as may be required by the scenario), direct radiation measurements, operation of vehicles, communication equipment, sampling equipment, and recordkeeping. The scenario is developed and the drills are conducted and critiqued by the site or EP.
14.1.3 Rad Protection Drills Rad Protection drills are conducted twice each calendar year for the CRN Site. These drills involve response to, and analysis of, simulated elevated airborne samples and direct radiation readings in the plant. The scenario is developed and the drills are conducted and critiqued by the site.
14.1.4 Radio Chemistry Drills Radiochemistry drills are conducted each calendar year at the CRN Site. These drills involve collecting and analyzing in-plant liquid and gaseous samples containing actual or simulated elevated levels, including use or simulated use of the post-emergency sampling system. The scenario is developed and the drills are conducted and critiqued by the site.
14.1.5 Radiological Dose Assessment Radiological dose assessment drills are conducted at least twice each calendar year to test the procedures, calculation techniques, computer codes, and environmental assessment abilities of the CECC staff and support groups. These scenarios are developed and the drills are conducted and critiqued by EP.
14.1.6 Fire Drills Fire drills will be conducted at the CRN Site in accordance with, and as required by, specific procedural requirements.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 14.1.7 Communications Drills Communications drills are conducted at least once each calendar year at the CRN Site.
14.2 EXERCISES Exercises are scheduled and conducted such that:
- A biennial exercise will be conducted for the CRN Site to test the REP every 2 calendar years. State of Tennessee participation in other TVA Exercises within the State determines if there will be full or partial participation by the State during CRN Site Exercises.
- The CRN Site ensures that adequate emergency response capabilities are maintained during the interval between biennial exercises by conducting drills, including at least one drill involving a combination of some of the principal functional areas of the onsite emergency response capabilities. (The principal functional areas of emergency response include activities such as management and coordination of emergency response, emergency assessment, protective action decision making, and plant system repair and corrective actions. During these drills supervised instruction is permitted, and activation of all of the emergency response facilities is not necessary. Sites have the opportunity to consider emergency management strategies, operating staff have the opportunity to resolve problems (success paths) rather than have controllers intervene, and the drills can focus on onsite training objectives. Sites shall enable the states and local authorities to participate in such drills when requested.)
- An exercise is conducted for the CRN Site, with full participation by State and local authorities, every two years. (Where a State has more than one site it shall participate fully every two years at some site and partially participate at the other sites offsite exercises.)
- An exercise is conducted for the CRN Site such that the State may exercise emergency plans related to ingestion exposure pathway measures every eight years. (Where a State has more than one site, this participation should be rotated between sites.)
- Major elements of the emergency plans and organizations are tested within an eight-year period.
- The CRN Site initiates an exercise between 6:00 p.m. and 4:00 am at least once every eight years. The exact time of the exercise is unannounced.
14.3 SCENARIOS Drills and exercises are conducted in accordance with scenarios that have been properly planned, researched, and developed.
The drill and exercise scenarios include, but are not limited to, the following:
- The basic objectives of each drill or exercise.
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- The date(s), time period, place(s), and participating organizations.
- The simulated events.
- A time schedule of real and simulated initiating events.
- A narrative summary describing the conduct of the exercises or drill, including simulated casualties, offsite fire department assistance, rescue of personnel, use of protective clothing, deployment of radiological monitoring teams, and public information activities.
Drill scenario development and implementation is the responsibility of the organization responsible for the specific drill.
Exercise scenario development and implementation is the responsibility of EP. Exercise scenario planning and development is coordinated with representatives of appropriate organizations and State agencies. Scenario specifics are not released by those representatives prior to the exercise.
Exercise scenarios will be developed to thoroughly test the REP on an eight year cycle. The exact time of an exercise is not released; however, a time span within which the exercise is to occur may be supplied to appropriate organizations and the news media so that the exercise is not confused with an actual emergency.
In the event a remedial exercise is required, a scenario is developed to demonstrate corrective measures have been taken regarding the described deficiencies.
14.4 CRITIQUES Representatives of Quality Assurance, INPO, NRC, DHS, State/local agencies and others may observe the exercise. Additional evaluators may be requested from other organizations as necessary. Evaluators are provided with sufficient material and a briefing prior to the exercise to become familiar with the Emergency Plan and exercise scenario.
At the conclusion of each exercise, a critique is conducted where the exercise and its participants are evaluated for effectiveness, procedural compliance and good practices. EP evaluates critique comments, develops a formal written report, coordinates corrective actions for deficiencies or items needing improvement, and follows up to ensure completion of corrective actions.
Drill critiques, critique reports, coordination of corrective action and follow-up to ensure completion is the responsibility of the organization administering the drill.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 15.0 TRAINING TVA ensures that personnel with specific duties and responsibilities in the NP-REP receive instruction in the performance of these duties and responsibilities.
15.1 ONSITE Site Nuclear Training/line organizations/site EP provide training in emergency procedures to permanent plant personnel and applicable non-plant personnel in accordance with plant training procedures.
For personnel with specific duties involving the NP-REP, this training consists of initial training classes and annual retraining to maintain familiarity with the features of the NP-REP.
Participation in drills, while not a requirement, does augment the training of those personnel who do participate. The site EP group provides training to key site responders in the TSC and OSC, and the SED.
Training for Plant Access is conducted in accordance with applicable CRN Site security procedures.
The Safety and Emergency Response Training Academy (SERTA) provides emergency medical care training to medical personnel and selected Nuclear Power personnel stationed at the CRN Site. Successful completion of training commensurate with their duties allows personnel to fulfill the role of medical care provider on the site MERT.
15.2 OFFSITE CECC personnel have current fitness for duty training. EP is responsible for ensuring that lesson plans are developed and training is conducted for CECC personnel. Training provided under this Plan is documented on an annual basis. Such documentation includes the date of the training, the names of those trained, and the training administered.
Training and annual retraining are provided to local plant support agencies (security, fire, ambulance, and hospital personnel) who may be involved with direct support of the site during an emergency.
Nuclear Support Services is responsible for providing agreement hospital and ambulance support training. The CRN Site is responsible for providing fire support training, with assistance from Nuclear Support Services, as needed. The CRN Site is responsible for providing local law enforcement (security) training. Training includes procedures for notification, basic radiation protection, expected roles, and site access procedures (as applicable).
15.3 PROFESSIONAL DEVELOPMENT TRAINING Full time EP staff members are afforded formal professional development training or activities commensurate with their duties and experience.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 16.0 PLAN MAINTENANCE 16.1 NP-REP Document Identification The CRN NP-REP has a controlled copy number.
Each page of the CRN NP-REP contains the following information:
NP-REP NP-REP Page 1 -or- Appendix A Rev. 1 Page A-1 Rev.1 Documents referenced in Appendix A, Attachment 1 are issued in accordance with appropriate State procedures.
Periodic Review The CRN NP-REP and the appendices are reviewed by CRN Site and EP staff annually for accuracy, completeness, operational readiness, and compliance with existing regulations and established policy. This review is initiated by EP and results are documented.
TVA has agreements with outside organizations for radiological emergency support to furnish specific services. Copies of the letters documenting these agreements are forwarded to EP and are reviewed annually and updated as necessary by EP.
Changes Revision to the CRN NP-REP may result from the reviews described in Subsection 16.1, drills, exercises, or changes in regulations. Changes are made and distributed according to Figure 16-
- 1. Changes identified from these reviews and drills and exercises are made as expeditiously as possible and are not necessarily held for submittal with an annual review.
Each line affected by a particular revision is marked in the margin. Changes in a revision are stated in the Revision Log; the pages affected and a brief explanation of the change are included in the Revision Log.
Plant Operations Review Committee (PORC) approval is obtained on CRN NP-REP revisions to Appendix A prior to their implementation. Changes to the main body of the CRN NP-REP and Appendices are scheduled for PORC review (up to 30 days based on the volume and complexity of the change). If comments cannot be resolved by the Director, Emergency Preparedness, and responsible site management, the comment is escalated to higher line management up to and including the TVA Chief Nuclear Officer and Executive Vice President.
Changes to the CRN NP-REP are approved by the General Manager, Support Services, or designee.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Distribution The CRN NP-REP, its additions, and revisions are authorized by an approval form and distributed by MS.
MS issues controlled revisions and ensures CRN NP-REP holders have received changes by requiring that copy holders sign a receipt, which is provided, and return it within two weeks.
MS maintains a historical file of superseded REP material.
To provide REP holders with assurance that the Plan is up-to-date, cover pages and revision logs are distributed with each revision or addition. The revision log lists the latest revision number, the date revised, pages revised, and the reason for the revision.
16.2 EPIPs 16.2.1 Document Identification The CRN Site and CECC EPIP manuals bear a copy number. Pages of controlled documents are issued in accordance with approved procedures. Each page contains the following information similar to the following example:
CECC-EPIP-1 Page 5 of 12 Rev. 1 Each procedure in an EPIP manual has a cover page listing the revision number and the effective date. Each procedure also has a revision log or description of the revision. The procedure revision approval form is signed by the approving authority (or their designee) responsible for that EPIP as listed below:
EPIPs Approving Authority CECC Director, Emergency Preparedness CRN Plant Manager, CRN Site 55 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Draft Proposed Change to NP-REP or Appendix Plan Effectiveness Determination (PED)
(In Accordance With 10 CFR 50.54(q))
Site Review in Accordance With Approved Procedures (Sites Are Not Required To Review and Approve Other Sites Appendices)
EP Review/Coordination and Approval Vice President Support Services, or Representative No Significant Change As Yes Determined by PED?
NRC Review and Approval MS Issues Revision Figure 16-1 Update Procedure for NP-REP and Appendices 56 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 16.2.2 Periodic Review The EPIPs are reviewed annually for accuracy, completeness, operational readiness, and compliance with existing regulations by the responsible organization listed below. This review is initiated by Nuclear Support Services and results are documented.
EPIPs Organization CECC REP Staff CRN CRN Site EP coordinates a quarterly review of notification lists in the Radiological Emergency Notification Directory (REND). The review covers phone numbers and names and is documented by the REND Revision Log.
16.2.3 EPIP Changes CECC-EPIP Changes Revision to a CECC-EPIP may result from the reviews described in Section 16.2.2, drills and exercises, or changes to regulations. Changes are made and distributed according to Figure 16-
- 2. EPIPs receive a review in accordance with 10 CFR 50.54(q) screening process consistent with the REP.
Each line affected by a particular revision is marked. Changes in a revision are stated in the Revision Log; the pages affected and a brief explanation of the change are included in the Revision Log.
CRN-EPIP Changes Permanent, temporary, and emergency CRN-EPIP changes are issued as controlled documents to plant document holders in accordance with CRN Site document control practices. MS issues the changes to other document holders in accordance with MS document control practices.
CRN-EPIPs receive a review in accordance with 10 CFR 50.54(q) screening process consistent with the REP.
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Proposed Change Proposed Change to CECC-EPIP to Site-EPIP Review, Coordination, Review and and Approval
- Coordination
- Director, Emergency Preparedness Site Review and Approval According Review and Approval to Approved Procedures MS Issues CECC-EPIP MS Issues Revision to Onsite and Offsite Site-EPIP Revision Document Holders to Onsite Document Holders MS Issues Site-EPIP Revision to Offsite Document Holders
- EPIPs receive review in accordance with 10 CFR 50.54(q)
Screening process consistent with the REP.
Figure 16-2 Update Procedure for EPIPs 58 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 16.2.4 Distribution Each CECC-EPIP or revision is authorized by an approval form and distributed by MS. CRN-EPIP changes are distributed as discussed in Section 16.2.3.
Upon receiving revision from EP, those who are assigned controlled copies of an EPIP sign a receipt, which is provided, and return it within two weeks to MS.
Each revision is accompanied by a revised cover page for that procedure. MS maintains a historical file on superseded CECC-EPIP material and the site maintains a historical file on superseded CRN-EPIP material.
16.3 DOCUMENT RELATIONSHIPS The NP-REP and the associated supporting plans and procedures are issued as separate documents.
TVA maintains the following documents:
- NP-REP.
- CECC-EPIP.
- CRN-EPIP.
- REND.
- Evacuation Time Estimate Manual.
- On-shift Staffing Analysis Report (CRN Site).
- Evaluation and Analysis of the ANS for the CRN Site.
These documents, along with the State Plan referenced in Appendix A, Attachment 1, may be issued separately or in combinations as applicable for the individual document holder.
16.4 AUDITS Quality Assurance conducts audits/reviews of the NP-REP program in accordance with 10 CFR 50.54(t) for compliance with existing regulations and its own internal requirements.
It is also responsible for offering recommendations on overall Plan improvement.
The results of the audit/review are documented, reported to appropriate organization management, and retained in the files for a period of five (5) years.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 16.5 AGREEMENT LETTERS This Section includes a listing of agreements or contracts maintained for services of outside organizations during an emergency. The detailed agreements with the Tennessee Emergency Management Agency, the Department of Energy, Roane County, and the City of Oak Ridge will be addressed at COLA and documented in a Multi-Jurisdictional Emergency Response Plan.
- Agreement letters for offsite law enforcement support are maintained by CRN Site Nuclear Security Services and are updated annually. These agreement letters may be examined upon obtaining approval from the site Nuclear Security Services Manager.
- Agreement letters with other offsite organizations are maintained by EP.
- Agreements are maintained with ambulance services for 24-hour availability of EMT-staffed ambulances for the transport of irradiated/contaminated patients.
- Agreements are maintained with fire departments having 24-hour assistance capabilities.
- Agreements are maintained with DOE REAC/TS, Oak Ridge, Tennessee and the University of Tennessee Medical Center, Knoxville, Tennessee. Both medical facilities can provide 24-hour availability to TVA for medical/radiological emergencies which exceed in house capabilities.
INPO provides assistance in locating and arranging additional emergency manpower, equipment, and the services of various technical experts from industry sources. INPO maintains this utility data in the INPO Emergency Resources Manual.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ) 17.0 DEFINITIONS AND ACRONYMS Activated - Minimum Activation Staff Positions are present onsite or in the facility within the assigned time following emergency declaration and ready to assume assigned functions.
Turnovers should be done as soon as practical, with consideration to performing them after the facility is activated.
Annual - Any 12 months, plus or minus 3 months with the following exceptions:
- TVA executes annual activities associated with exercises, drills, emergency information for residents, media training, and offsite emergency response training are defined as "once per calendar year."
- TVA annual training is for a 12-month period which includes a grace period extending to the end of the calendar quarter in which training is due.
ANI - American Nuclear Insurers.
CECC (Central Emergency Control Center) - The offsite TVA emergency response facility located in Chattanooga, Tennessee, with the overall TVA responsibility for response to an emergency. It consists of a director and staff to coordinate and direct TVAs efforts during the emergency.
CECC-EPIPs (Central Emergency Control Center Emergency Plan Implementing Procedures) -
The set of emergency response procedures developed to ensure that the capabilities described in Part 5B of the CRN Site ESPA are fulfilled in the CECC and offsite.
COC - TVA Chattanooga Office Complex, Chattanooga, Tennessee.
CRN Site - The Clinch River Nuclear Site.
CRN-EPIPS (Clinch River Nuclear Site Emergency Plan Implementing Procedures) - The set of CRN Site emergency response procedures developed to ensure that the capabilities described in Part 5B of the CRN Site ESPA are fulfilled at the CRN Site.
DHS - U.S. Department of Homeland Security.
DOE - U.S. Department of Energy.
DOT - U.S. Department of Transportation.
Drill - A supervised instruction period aimed at testing, developing, and maintaining skills in a particular operation. A drill is often a component of an exercise.
EAL (Emergency Action Level) - Specific events and criteria used to determine the appropriate emergency classification.
EDO - Emergency Duty Officer.
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Emergency Classification (Also Class or Classification) - A scheme derived to categorize a plant emergency into one of four classes according to severity so that appropriate actions might be rapidly taken.
EMT (Emergency Medical Technician) - An individual certified under a recognized TVA system to provide emergency and related services to victims of illness or injury.
ENS (Emergency Notification System) - The phone line used to notify and inform the NRC of Event Status Data.
Environs - The atmospheric, terrestrial, and aquatic areas outside the site boundary.
EOC - Emergency Operations Center.
EP Staff - Emergency Services, Emergency Preparedness Staff.
EPA - U.S. Environmental Protection Agency.
EPZ (Emergency Planning Zone) - The area surrounding the site for which planning is performed to prepare to respond to a nuclear plant emergency. The two zones are (1) plume exposure pathway EPZ; (2) ingestion exposure pathway EPZ.
Exclusion Area Boundary - The area for which TVA has absolute authority for exclusion of personnel and property within the site boundary. This boundary is used in SSAR dose assessments to define the distance to the first member of the public and is defined in the SSAR.
Exercise - An event that tests the integrated capability and a major portion of the basic elements existing within the Emergency Plan.
FEMA (Federal Emergency Management Agency) - An agency of the federal government.
Hostile Action - An act toward a nuclear site or its personnel that includes the use of violent force to destroy equipment, takes hostages, and/or intimidates the licensee to achieve an end.
This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included. Hostile Action should NOT be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the nuclear site.
Hostile Force - One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
HPN (Health Physics Network) - The NRCs health physics information line.
IC - (Initiating Condition) - An event or condition that aligns with the definition of one of the four emergency classification levels by virtue of the potential or actual effects or consequences.
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INPO - Institute for Nuclear Power Operations.
JIC (Joint Information Center) - A center established near the CRN Site to assist the news media in providing press coverage during an emergency.
LRC (Local Recovery Center) - A facility located near the CRN Site used as additional office space, if necessary, for TVA personnel during recovery operations. The facility is also available for NRC use during an emergency. Additionally, the LRC may serve as an alternate emergency response facility if needed, and can also serve as a staging area for individuals or teams prior to dispatch to the CRN Site.
MASP - Minimum Active Staffing Positions.
MERT - Medical Emergency Response Team.
Missiles - As used in the EALs, a missile is any hurled object (e.g., debris from explosions, fragments from rotating equipment breaks).
Monthly - Any 30-day period, plus or minus 7 days.
MS - Management Services.
NOAA - National Oceanic and Atmospheric Administration.
NOUE - Notification of Unusual Event.
NP - Nuclear Power.
NP-REP (Nuclear Power Radiological Emergency Plan) - The Plan which provides the policies and the actions to be used to minimize the impact on personnel, public, and the environment from an emergency at a TVA nuclear plant.
NRC - U.S. Nuclear Regulatory Commission.
NRF - National Response Framework.
NSS - Nuclear Security Services.
NSSS - Nuclear Steam Supply System.
Offsite - The area around a nuclear plant site that is not onsite.
Onsite - Onsite is defined according to the subject ... (1) in relation to SSAR dose assessment, onsite is "within the exclusion area;" (2) in relation to accountability and site notifications, onsite is "within the site's outermost secured area;" (3) in relation to EP dose assessments onsite is defined as "1000 meter radius;" and (4) in other contexts onsite is "within the reservation boundary."
ODS (Operations Duty Specialist) - The 24-hour per day emergency contact for TVA.
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ORAU (Oak Ridge Associated Universities) - A nonprofit corporation and prime contractor with DOE for operation of the REAC/TS facility.
ORMMC (Oak Ridge Methodist Medical Center) - In conjunction with the REAC/TS facility, provides continuing medical care to radiological emergency victims.
OSC (Operations Support Center) - An area set aside within the plant for providing an assembly area for operational support personnel during an emergency situation.
PABX (Private Automatic Branch Exchange) - A communications system, controlled by TVA, employing microwave and land line transmissions.
PAR - Protective Action Recommendation.
Plant Manager - Key plant management serving as the Shift Manager's supervisory contact during off-hours.
PORC (Plant Operations Review Committee) - A group of plant supervisors whose function is to provide a safety review of procedures and operations for the plant and make recommendations to the Plant Manager on these matters.
Quarterly - Any three-month period, plus or minus one month.
RAA - Radiological Assessment Area of CECC.
Rad Protection - Radiological Protection.
R or r - For purposes of this Plan and its implementing procedures, radiation exposure as expressed in units of R/hr and subunits, thereof, is equivalent to dose (rad) and dose equivalent (rem).
RCI - Radiological Control Instructions.
REAC/TS (Radiation Emergency Assistance Center/Training Site) - A special facility that is operated by ORAU for DOE, to provide a sophisticated facility to handle radiological emergency victims. The REAC/TS facility is located in ORMMC.
Recovery - The post emergency activities in which the plant conditions are assessed and the plant is returned to an operational mode.
REND (Radiological Emergency Notification Directory) - A directory of key personnel for support of the CECC.
REP - Radiological Emergency Plan.
RMCC (Radiological Monitoring Control Center) - An environmental monitoring coordination center.
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SAE - Site Area Emergency.
Security Condition- Any Security Event as listed in the approved Security Contingency Plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A Security Condition does NOT involve a Hostile Action.
SED - Site Emergency Director.
Semiannual - Any six-month period, plus or minus 45 days. (The exception to this is for drills for which it is defined as "twice each calendar year.")
SEOC- State Emergency Operations Center.
Site Boundary - The appropriate boundary between "onsite" and "offsite."
SSAR (Site Safety Analysis Report) - The report required by 10 CFR 52.17(a)(1) to be included in each application for an early site permit. The SSAR includes a description of the facility, the maximum levels of thermal and radiological effluents, and a description of seismic, meteorological, hydrologic, and geologic characteristics of the proposed site.
SM - Shift Manager.
TEDE - Total Effective Dose Equivalent as defined by 10 CFR 20.1201.
TSC (Technical Support Center) - An assembly/work area for designated support individuals knowledgeable of and responsible for engineering and management support of reactor operations in the event of an emergency.
UE (Unusual Event) - terminology that is commonly used referring to the term Notification of Unusual Event (NOUE). UE and NOUE are synonymous.
WARL (Western Area Radiological Laboratory) - TVA laboratory located in Muscle Shoals, Alabama, capable of analyzing environmental samples for radioactive content.
Weekly - Any seven-day period, plus or minus two days.
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Attachment 1 Justification for the Central Emergency Control Center Under 10 CFR Part 50, Appendix E, Section IV.E.8, TVA is required to provide a licensee near-site Emergency Operations Facility (EOF) from which effective direction can be given and effective control can be exercised during an emergency. The NRC provides guidance for design and location of the EOF in NUREG-0696, Functional Criteria for Emergency Response Facilities (NUREG-0696). Since the early 1980s, TVA has used a centralized concept for providing the EOF function for its nuclear sites. Consistent with this approach, the CRN Site Emergency Plan relies on the use of the Central Emergency Control Center (CECC) as the EOF for the CRN Site. The CECC serves as the EOF for the other TVA nuclear plants (Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN)). The CECC is located in the TVA Chattanooga Office Complex (COC) in Chattanooga, Tennessee, approximately 78 air miles from the CRN Site. The CECC is further than 20 miles from the CRN Site Technical Support Center (TSC), as is the case for BFN, SQN, and WBN, but does not alter the functions of the EOF as described in NUREG-0696.
The use of the CECC as the EOF for the CRN Site allows TVA to continue to operate a standardized program for corporate management and response to radiological emergencies at TVA nuclear facilities. The effectiveness of CECC operations has been demonstrated during numerous drills and exercises. Communications systems, data links, and staffing have been incorporated and tested. Using the CECC for the CRN Site also allows TVA to apply its corporate emergency response structure and experience to the CRN Site Emergency Plan.
TVA has discussed this concept with the Tennessee Emergency Management Agency (TEMA).
TEMA is familiar with the CECC because the facility is used for responding to radiological emergencies at SQN and WBN. Through the letter referenced in SSAR, Section 13.3 of the CRN ESPA, TEMA confirms their support of the TVA emergency response program, included the use of the CECC in Chattanooga.
Access to the station by the NRC site team is accommodated. The CRN Site has a Local Recovery Center (LRC) which is a pre-designated facility dedicated for use by offsite TVA and NRC personnel that may be assigned to the CRN Site for recovery operations. In addition, the LRC may be used by the NRC during the event as an area near the site for assessment and assistance and has the capability to communicate offsite. Additional information regarding the LRC can be found in section 8.1.3 of this Plan and in A.4.8 in Appendix A.
The CECC includes space for State liaisons reporting to the CECC in Chattanooga.
The following discussion provides an evaluation of the CECC against the criteria provided in NUREG-0696.
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Evaluation Against NUREG-0696:
The CECC is designed to provide for the effective and timely performance of the following functions:
- Management of overall licensee emergency response.
- Coordination of radiological and environmental assessment.
The primary role of the CECC is to relieve the plant staff of the functions of keeping the federal, State, and county emergency response organizations informed, for directing dose assessment and field monitoring, for managing the informational needs of the media, interested industry groups, and elected officials, and for supporting the emergency assessment needs of the TSC staff. The NRC will have access to plant data through the CECC computer system and the Emergency Response Data System (ERDS). The NRC also has telephones on the Emergency Telecommunications System (ETS) in Chattanooga.
Equipment exists in the CECC for the acquisition, display, and evaluation of radiological, meteorological, and plant system data. Because a similar set of data currently used for BFN, SQN, and WBN are required for the CRN Site, the plant and effluent data would be provided on as timely a basis at the CECC as it would be at a near-site location.
Normal industrial security is already provided for the CECC and processes are already established to upgrade the security of the facility during an activation.
Location, Structure, and Habitability The CECC is located in the northeast corner of the sixth floor of Lookout Place in the TVA COC in Chattanooga, Tennessee. The CECC has proven to be an effective facility for implementation of the TVA nuclear station emergency plans. The CECC is used for existing TVA nuclear plants at the BFN, SQN, and WBN sites. The facility is more than ten miles from any of the TVA nuclear stations; therefore, there are no specific habitability criteria.
Staffing and Training Incorporation of CRN emergency response functions into the CECC will not adversely affect the ability of TVA to staff the CECC in a timely manner. The CECC is staffed with experienced personnel from the TVA COC and personnel from one or more TVA nuclear plants. The CECC staff has demonstrated their ability to staff the CECC within required time-frames following emergency declaration during previous staff augmentation drills. The CECC staff includes personnel to manage overall licensee emergency response, and coordinate radiological and environmental assessment.
Size The CECC size has proven to be adequate during drills and exercises for the existing TVA nuclear facilities. In addition, the NRC has workspace co-located with the decision makers, radiological assessment, and emergency assessment personnel.
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Radiological Monitoring The CECC is beyond 10 miles from any nuclear stations, and therefore does not require radiological monitoring equipment.
Communications The communications systems available in the CECC consist of:
- Central Office Trunks.
- Tie-lines.
- Digital Services.
- Privately-owned/maintained microwave systems.
- Privately-owned fiber-optic systems.
- NRC ETS phones.
- EP Radio System.
The emergency communications systems at the CECC are designed to provide a reliable, timely flow of information between the parties having an emergency response role. The single facility results in commonality of communications and interface with offsite officials and liaisons. The EP telephone system continues to be the primary means of communicating changes in event classification. This system operates on a combination of the TVA telecommunications network and leased circuits.
The offsite communications network is used to communicate with federal, State, and other supporting agencies. Access to these agencies is provided through several redundant, diverse routes. This diversity provides offsite routing through more than one type of facility. These facilities include, but are not limited to, commercial facilities such as central office trunks, tie-lines and digital services, plus privately owned and maintained microwave and fiber-optic systems. The offsite telecommunications network is designed to facilitate traffic in the most fail-safe manner to the emergency response organizations.
The Emergency Notification System (ENS) and Health Physics Network (HPN) (NRC FTS 2000 System) communication systems provide communications from each site TSC, Control Room, and the CECC to the NRC Headquarters and regional offices. These telephones are tested on a periodic basis consistent with the CRN Site Emergency Plan.
The EP radio system is a VHF mobile radio system which provides redundant radio coverage of the Plume Exposure Pathway (PEP) Emergency Planning Zone (EPZ) and provides radiological monitoring vehicles with mobile communications to other vehicle(s) and to the following locations: Radiological Control, TSC, Control Room at each TVA plant, and the CECC.
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Instrumentation, Data System Equipment, and Power Supplies Various plant parameters are available to the CECC staff via a connection through the TVA CECC computer network. Data available at the CECC provides a snapshot of data from each units integrated set of plant data. Plant data can be displayed at the CECC. These data are sufficient to perform emergency assessment and evaluate the potential environmental consequences of an emergency at the CRN Site. Detailed discussion on CRN Site plant-specific parameters are described in the Emergency Plan. The computers in the dose assessment area are capable of running the dose projection computer programs and accessing plant status data.
Hourly and 15-minute average meteorological data from the plant Environmental Data Station are available to the CECC, TSC, State, and LRC. The CECC computer system provides access to up to the most recent 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of this data. A meteorologist in the CECC provides meteorological information to the CECC staff in support of offsite dose projections.
The CECC draws its primary power from commercial power. A loss of commercial power should not impact any of the voice or data communications equipment located in the CECC. Common TVA telecommunications infrastructure that supports CECC functions, including, but not limited to fiber optic transmission equipment, telephone switching equipment, and data network routers, is configured to operate from at least one and usually multiple backup power sources in the event of a loss of commercial power. These backup sources include generator, dc battery and uninterruptible power supply systems.
Technical Data and Data Systems As discussed in the previous section, a variety of plant parameters are provided over the TVA communications network to the CECC.
Reports Availability and Management Hard copies of key reference materials are maintained in the CECC. In addition, station design documentation, plant drawings, procedures, etc. are available via Local Area Network connection from the Business Support Library.
The following information is available for the CRN Site at the CECC:
- Plant technical specifications.
- Plant operating procedures.
- Emergency operating procedures.
- Final Safety Analysis Report.
- Up-to-date licensee, State, and local emergency response plans.
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Conclusion The CECC meets the functional and design criteria provided in NUREG-0696 for an EOF with the exception that it is located more than 20 miles from the CRN Site. This document describes the TVA approach to assuring that these functional and design criteria are met and maintained.
The consolidation of TVA corporate emergency response functions into a centralized facility provides a timely and effective response to a radiological emergency at the CRN Site.
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Appendix A Revision 1
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Appendix A Table of Contents A.1 CLINCH RIVER NUCLEAR SITE AND EMERGENCY PLANNING ZONE DESCRIPTION .................................................................................................... 1 A1.1 FACILITY AND SITE CHARACTERISTICS ................................................... 1 A.1.1.1 Nuclear Power Facility .................................................................................. 1 A.1.1.2 Site Location And Description ..................................................................... 1 A.1.2 EMERGENCY PLANNING ZONES ................................................................ 1 A.2 EMERGENCY ACTION LEVELS ....................................................................... 3 A.3 SITE EMERGENCY ORGANIZATION (CONCEPT OF OPERATIONS) .......... 4 A.3.1 OPERATIONS ................................................................................................. 4 A.3.2 FIRE PROTECTION ........................................................................................ 4 A.3.3 RADIATION PROTECTION (RP) / CHEMISTRY ........................................... 4 A.3.4 SECURITY ...................................................................................................... 4 A.3.5 MAINTENANCE .............................................................................................. 4 A.3.6 ONSITE EMERGENCY MANAGEMENT ORGANIZATION ........................... 4 A.3.6.1 Site Vice President ........................................................................................ 5 A.3.6.2 Site Emergency Director ............................................................................... 5 A.3.6.3 Operations Manager ...................................................................................... 6 A.3.6.4 Technical Assessment Manager .................................................................. 6 A.3.6.5 Nuclear Security Manager ............................................................................ 6 A.3.6.6 Radiological Protection Manager ................................................................. 7 A.3.6.7 Chemistry Manager ....................................................................................... 7 A.3.6.8 Osc Manager .................................................................................................. 7 A.3.6.9 Osc Rad Protection Representative ............................................................ 8 A.3.6.10 Other Osc Representatives .......................................................................... 8 A.4 EMERGENCY RESPONSE FACILITIES, EQUIPMENT, AND SUPPLIES .... 11 A.4.1 TECHNICAL SUPPORT CENTER ................................................................ 11 A.4.2 OPERATIONS SUPPORT CENTER ............................................................. 13 A.4.3 LABORATORY AND EQUIPMENT .............................................................. 13 A.4.4 ONSITE MONITORING SYSTEMS AND EQUIPMENT ............................... 13 A.4.4.1 Natural Phenomena ..................................................................................... 14 A.4.4.2 Radiological Monitors ................................................................................. 14 A-ii Revision 1
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Appendix A A.4.4.3 Process Monitors (Non-Radiological) ....................................................... 14 A.4.4.4 Safety Parameter Display System (Or Equivalent) ................................... 14 A.4.4.5 Emergency Response Data System .......................................................... 15 A.4.4.6 Fire Protection ............................................................................................. 15 A.4.4.7 Environment................................................................................................. 15 A.4.5 EMERGENCY EQUIPMENT ......................................................................... 16 A.4.5.1 Emergency Communications Equipment ................................................. 16 A.4.5.2 First Aid And Medical Facilities ................................................................. 16 A.4.6 ADDITIONAL LOCAL SUPPORT ................................................................. 17 A.4.6.1 Fire ................................................................................................................ 17 A.4.6.2 Law Enforcement......................................................................................... 17 A.4.6.3 Vendor Support ........................................................................................... 17 A.4.7 ASSEMBLY/ACCOUNTABILITY ALARM .................................................... 17 A.4.8 LOCAL RECOVERY CENTER ..................................................................... 17 A.5 MAINTAINING EMERGENCY PREPAREDNESS .......................................... 18 A.5.1 Responsibility For The Emergency Preparedness Effort ........................ 18 A.5.2 Procedures ................................................................................................... 18 A.5.3 INDEPENDENT REVIEWS OF EMERGENCY PREPAREDNESS .............. 18 A.6 ALERT AND NOTIFICATION SYSTEM ........................................................... 19 A.7 TRAINING AND DRILLS .................................................................................. 20 A.7.1 TRAINING PERSONNEL .............................................................................. 20 A.7.2 DRILLS AND EXERCISES ........................................................................... 20 A.8 EMERGENCY PLAN IMPLEMENTING PROCEDURES ................................ 21 State Multijurisdictional Radiological Emergency Response Plan ........... 22 Emergency Equipment And Supplies ........................................................... 23 Cross Reference To Regulations And Guidance ......................................... 24 A-iii Revision 1
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Appendix A A.1 CLINCH RIVER NUCLEAR SITE AND EMERGENCY PLANNING ZONE DESCRIPTION A.1.1 FACILITY AND SITE CHARACTERISTICS A.1.1.1 Nuclear Power Facility The Clinch River Nuclear (CRN) Site is located on the Clinch River Property and is used as the location to construct and operate Small Modular Reactors (SMRs).
A.1.1.2 Site Location and Description The CRN Site Property covers an area of approximately 1,200 acres located adjacent to the Clinch River in Roane County, Tennessee. The CRN Site lies north of U.S. Interstate 40, approximately midway between the communities of Harriman and Farragut in the eastern portion of Tennessee.
Site Safety Analysis Report (SSAR) Chapter 2 provides additional information regarding the physical characteristics of the proposed site, including the preliminary site layout and potential hazards in the site vicinity. The Environmental Report provides detailed information addressing land use and other features of the proposed site and surrounding area.
The CRN Site Early Site Permit Application (ESPA) includes an Evacuation Time Estimate (ETE) Report, which provides the results of public evacuation analyses conducted in accordance with the guidance provided in NUREG/CR-7002, Criteria for Development of Evacuation Time Estimate Studies. The analyses reflected in the ETE Report did not identify physical characteristics unique to the proposed site that could pose a significant impediment to the development of emergency plans.
A.1.2 EMERGENCY PLANNING ZONES Section 50.47(c)(2) of 10 CFR 50 establishes two Emergency Planning Zones (EPZs) for consideration in nuclear power plant emergency planning. For the CRN Site, the plume exposure pathway (PEP) EPZ encompasses an area approximately 2 miles in radius surrounding the site. The ingestion exposure pathway EPZ encompasses an area that is yet to be determined. TVA intends to address this in the CRN Site Combined License Application (COLA).
In addition to the basic requirements for EPZ radius, development of the EPZs includes consideration of local emergency response needs and capabilities, including considerations of demography, topography, land characteristics, access routes, and jurisdictional boundaries. Of particular interest in the development of the CRN Site PEP EPZ is the overlapping emergency planning zone for the U.S. Department of Energy (DOE) Oak Ridge Reservation.
Figure A.1-1 provides a map of the PEP EPZ for the CRN Site.
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Appendix A Figure A.1-1 Plume Exposure Pathway Emergency Planning Zone A-2 Revision 1
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Appendix A A.2 EMERGENCY ACTION LEVELS Part 5B Section 4.2 indicates that recognition of the emergency class is primarily a judgment matter for plant personnel. The initiating conditions (ICs) used for recognizing and declaring the emergency class are based on specific measurable values or observable conditions defined as Emergency Action Levels (EALs). These can be combinations of specific instrument readings (including their rates of change), annunciator warnings, and time periods during which certain conditions exist, etc. CRN Site Emergency Plan Implementing Procedures (CRN-EPIPs) provide details regarding instrument readings and parameters required for determination of these EALs.
Tennessee Valley Authority (TVA) uses these EALs as thresholds for determining the emergency classifications. TVA develops the EALs based on industry guidance, engineering assessments, and insights provided by the reactor plant supplier.
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Appendix A A.3 SITE EMERGENCY ORGANIZATION (CONCEPT OF OPERATIONS)
TVA maintains an organization capable of responding to a radiological emergency. The on-shift staff is continually present on a 24-hour basis. TVA will specify on-shift staffing at COLA. The on-shift staffing would be evaluated pursuant to Section IV.A.9 of Appendix E of 10 CFR 50.
A.3.1 OPERATIONS The minimum staff required to conduct routine and immediate emergency operations is maintained at the station consistent with 10 CFR 50.54(m) and the facility Technical Specifications. Staffing is described in SSAR Section 13.1. Site procedures provide the details of the normal site organization, including reporting relationships.
A.3.2 FIRE PROTECTION The Fire Shift Operations is staffed by qualified personnel that meet the requirements established in the CRN Site Fire Protection Plan.
A.3.3 RADIATION PROTECTION (RP) / CHEMISTRY The RP/Chemistry is staffed by qualified personnel that meet the requirements established in the CRN Site Technical Specifications.
A.3.4 SECURITY Security is staffed by qualified personnel that meet the requirements established in the CRN Site Physical Security Plan.
A.3.5 MAINTENANCE Maintenance is staffed by personnel who are available to respond to postulated events that could involve one or more of the three commonly recognized technical disciplines; mechanical, electrical, or instrumentation. Each maintenance team member has a background in one or more discipline(s). Team members may perform cross-disciplinary work if they have a background to perform the respective task/activity. The Maintenance team members provide a first response capability within the bounds of the actions required during the initial phase of a radiological emergency.
A.3.6 ONSITE EMERGENCY MANAGEMENT ORGANIZATION CRN-EPIPs describe the duties and responsibilities of the Onsite Emergency Management Organization positions. Figure A.3-1 illustrates the organization for the Technical Support Center (TSC), including those positions that must respond within a prescribed period of time following an Alert or higher emergency declaration. The prescribed period of time for responding to the TSC will be addressed in the CRN Site COLA. Figure A.3-2 illustrates the organization for the Operations Support Center (OSC).
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Appendix A A.3.6.1 Site Vice President The Site Vice President:
- Serves as a corporate interface for the Site Emergency Director (SED), relieving them from duties which could distract from the SED primary purpose of plant operations and emergency mitigation activities.
- Provides assistance to the SED by providing TVA policy direction; directing site resources to support the SED in emergency mitigation activities; and providing a direct interface on overall site response activities with the U.S. Nuclear Regulatory Commission (NRC), the U.S. Department of Homeland Security (DHS), or other federal organizations responding to the site, Central Emergency Control Center (CECC)
Director, or onsite media.
- At their discretion, may provide an interface at the appropriate offsite location on the overall site response activities with State and local agencies, NRC region/headquarters, or Joint Information Center (JIC).
- Provides support to other emergency operation centers as necessary.
A.3.6.2 Site Emergency Director The Site Emergency Director (SED) is located in the TSC and:
- Directs onsite emergency mitigation activities.
- Consults with the CECC Director, and Senior Site Executive on significant events and their related impacts.
- Identifies protective actions.
- Apprises the NRC with regard to emergency mitigation actions being taken.
- Makes final decision on personnel entrance to radiologically-hazardous areas when Radiological (Rad) Protection recommends against the entry.
- Initiates long-term 24-hour per day emergency mitigation operations.
- Determines the emergency classification.
- Makes recommendations for protective actions (if necessary) to the State and local agencies prior to the CECC being staffed (this responsibility can be transferred only to the CECC Director).
The SED or Control Room staff is responsible for making initial notifications to the appropriate State organization. The SED is also responsible for emergency dose authorizations for personnel under their direction and control (these responsibilities cannot be delegated).
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Appendix A A.3.6.3 Operations Manager The Operations Manager is located in the TSC and:
- Directs operational activities.
- Keeps the SED informed on plant status and operational problems.
- Performs damage assessment as necessary.
- Assures the Control Room is aware of the emergency assessment and response.
- Recommends solutions and mitigating action for operational problems.
A.3.6.4 Technical Assessment Manager The Technical Assessment Manager is located in the TSC and:
- Provides information, evaluations, and projections to the SED.
- Coordinates assessment activities with the CECC.
- Keeps the Technical Assessment Team informed of plant status.
- Assesses effluents.
- Directs the Technical Assessment Team.
- Projects future plant status based on present conditions.
The Technical Assessment Manager provides pertinent information to appropriate organizations via a continuously used and monitored telephone communications hookup.
A.3.6.5 Nuclear Security Manager The Nuclear Security Manager is located in the TSC and:
- Directs activities of Nuclear Security Services personnel.
- Controls access to site and Control Rooms.
- Reports on site accountability/evacuation as defined in CRN-EPIPs.
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Appendix A A.3.6.6 Radiological Protection Manager The Radiological (Rad) Protection Manager is located in the TSC and:
- Assesses in-plant and onsite radiological conditions.
- Directs onsite Rad Protection activities.
- Coordinates additional Rad Protection support with the CECC.
- Recommends protective actions for onsite personnel to the SED.
- Maintains the offsite radiological conditions status information.
- Coordinates assessment of radiological conditions with the CECC.
- Maintains the inplant radiological status boards.
- Assists the Maintenance Superintendent in briefing maintenance teams.
- Assigns appropriate Rad Protection support to maintenance teams.
- Makes final recommendation to the SED for personnel entry to radiologically hazardous environments.
A.3.6.7 Chemistry Manager The Chemistry Manager is not a minimum required staff position. When this position is staffed, the Chemistry Manager is located in the TSC and:
- Coordinates assessment of effluents with the CECC.
- Coordinates post-emergency sampling activities.
- Directs radiochemical lab activities.
- Assesses effects on radwaste and effluent treatment systems.
A.3.6.8 OSC Manager The OSC Manager is located in the Operations Support Center and:
- Directs repairs and corrective actions in coordination with the TSC.
- Performs damage assessment.
- Directs activities of OSC.
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Appendix A
- Coordinates maintenance teams and ensures they have received proper briefings and are accompanied by a Rad Protection Technician, as necessary.
A.3.6.9 OSC Rad Protection Representative The OSC Rad Protection Representative is located in the TSC and:
- Directs activities of the Rad Protection lab.
- Ensures Rad Protection coverage of damage repair teams.
A.3.6.10 Other OSC Representatives Other OSC representatives are located in the OSC and provide support to the OSC Manager within their respective technical disciplines. Responsibilities include:
- Providing and supervising personnel and other resources within their respective disciplines.
- Providing pre-job and post-job briefings to personnel.
- Communicating technical information to personnel located in the TSC.
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Appendix A Site Site Vice Emergency President Director Administrative Technical Support Advisor(s)
(as needed) (as needed)
Technical Radiation Operations Maintenance Assessment Protection Manager Manager Manager Manager Technical Support Support Support Assessment Staff Staff Staff Team Chemistry Manager Figure A.3-1 Technical Support Center Organization A-9 Revision 1
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Appendix A Operations Support Center Manager Administrative Support Security (as needed)
Safety Fire Protection (as needed)
Radiation Chemistry Operations Maintenance Protection Representative Representative Representative Representative Radiation Chemistry Operations Maintenance Protection Staff Staff Staff Staff Figure A.3-2 Operations Support Center Organization A-10 Revision 1
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Appendix A A.4 EMERGENCY RESPONSE FACILITIES, EQUIPMENT, AND SUPPLIES Specific plant areas, onsite and offsite facilities, and equipment are selected and provided for use during a radiological emergency at the CRN Site. The preselection, allocation, and inclusion of emergency facilities assure that needed services and equipment are available for use during emergency conditions.
A.4.1 TECHNICAL SUPPORT CENTER The CRN Site is equipped with a Technical Support Center (TSC). The TSC is part of the emergency response facilities provided for emergency response to accidents. The TSC is established consistent with NUREG 0696, Functional Criteria for Emergency Response Facilities (NUREG-0696), as described below.
Function The TSC provides plant management and technical support personnel (including the appropriate number of NRC personnel) with a facility from which they can assist plant operating personnel located in the Control Room during an emergency. The SED and the NRC representative are located in the same general area to promote proper communications.
Location The TSC has the ability to retrieve plant data and displays available in the Control Room and is equipped with sophisticated communications systems. This precludes the need for frequent face to face interchange between the TSC and Control Room personnel.
Staffing and Training The level of staffing and training is described in the Emergency Plan. The TSC accommodates the required personnel to support an emergency affecting the CRN Site. The level of staffing may vary according to the severity of the emergency condition.
Size The TSC provides working space, without crowding, for the personnel assigned to the TSC at the maximum level of occupancy. The working space is sized for a minimum of 25 persons.
Minimum size of working space is approximately 75 ft2 per person.
Structure The TSC is designed in accordance with the Uniform Building Code (UBC) to withstand earthquakes and high winds.
Habitability The ventilation system is operated in accordance with approved procedures and is manually controlled from the TSC. In addition, portable radiation monitors are available to personnel in A-11 Revision 1
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Appendix A the TSC. Equipment and supplies are provided in accordance with the Emergency Plan. The ventilation system includes high efficiency particulate air (HEPA) filters and charcoal filters. The ventilation system is designed to maintain exposures at or below (5 rem total effective dose equivalent (TEDE) as defined in 10 CFR 50.2 for the duration of an emergency. The TSC structure, shielding, and ventilation system are designed to protect the TSC personnel from radiological hazards.
Communications The TSC has reliable voice communications to the Control Room, the OSC, the CECC, and the NRC. Provisions for communications with State and local operations centers are also provided in the TSC. The communications facilities include the means for reliable primary and backup communication.
Instrumentation, Data System Equipment, and Power Supplies The TSC is provided with reliable power and backup power supplies. Lighting is powered by the normal and backup electrical supply system. An emergency battery operated lighting system is installed. Power for vital information systems is provided by reliable power supplies including a battery backed Uninterruptible Power Supply (UPS) system.
Technical Data and Data System Within the TSC, technical and operational data and information is available for each unit.
Support facilities are located within the TSC to support long term operation of the TSC. The TSC is equipped with a computer system which provides source term and meteorological data and technical data displays to allow TSC personnel to perform detailed analysis and diagnosis of abnormal plant conditions, including assessment of any significant release of radioactivity to the environment. Human Factors Engineering (HFE) is incorporated into the design of the TSC related to the display and availability of plant data.
Records Availability and Management The TSC has ready access to plant records. The documents maintained in the TSC include:
- Technical Specifications.
- Plant Operating Procedures.
- Emergency Operating Procedures.
- Final Safety Analysis Reports.
- System piping and ventilation diagrams and heating, ventilation, and air conditioning (HVAC) flow diagrams.
- Piping area diagrams.
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Appendix A
- Records needed to perform the functions of the CECC when it is not operational.
In addition, copies of the above-listed documents and the following documents are available in CRN Site Document Control:
- Plant operating records.
- Plant Review Board records and reports.
The above records are updated as necessary to maintain currency and completeness.
Operations at this facility are directed by the SED when the TSC is operational.
CRN-EPIPs describe the staffing and operation of the TSC.
A.4.2 OPERATIONS SUPPORT CENTER The site is equipped with an OSC. The OSC provides a centralized area and the necessary supporting resources for the assembly of designated operations support personnel during emergency conditions. The OSC provides the resources for communicating with the Control Room and the TSC. This permits personnel reporting to the OSC to be assigned to duties in support of emergency operations.
Designated plant support personnel assemble in the OSC to provide support to both the Control Room and TSC. The primary function of the OSC staff is to dispatch assessment, corrective action, and rescue personnel to locations in the plant, as directed by the TSC and Control Room. TVA provides for an OSC assembly area separate from the Control Room and the TSC.
Personnel reporting to the OSC can be assigned duties in support of emergency operations.
The OSC is not designed to remain habitable under all projected emergency conditions; however, implementing procedures make provisions for relocating the OSC as needed, based on ongoing assessments of plant conditions and facility habitability. The SED directs relocation of the OSC, if required.
CRN-EPIPs describe the staffing and operation of the OSC.
A.4.3 LABORATORY AND EQUIPMENT TVA provides laboratory facilities adequate for chemical and radiological analyses of relevant sample media, including solid, liquid, and air samples. The laboratory equipment provides capabilities to perform isotopic analyses of samples to identify radionuclides present in the samples and their concentrations per unit mass or volume, as appropriate.
A.4.4 ONSITE MONITORING SYSTEMS AND EQUIPMENT Information regarding onsite monitoring systems and equipment is addressed in the COLA.
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Appendix A A.4.4.1 Natural Phenomena In the event an emergency is the result of a natural phenomenon, there is instrumentation to monitor its severity. The Environmental Data Station is located onsite and contains instruments capable of measuring wind direction, wind speed, and temperatures. Seismic instrumentation is available in the plant to monitor acceleration levels of ground movement.
Hydrological monitoring systems are installed to supply flow and level information.
Meteorological and seismic instrumentation have readily accessible readout in the Control Room.
In the event of a failure of the onsite natural phenomena monitoring systems, TVA maintains access to back-up data sources. These back-up sources include telephone and web-based contact with federal government data sources and alternative sources, including university and news media sources.
A.4.4.2 Radiological Monitors The installed Radiation Monitoring System consists of process monitors and area monitors.
Additional information regarding this system is addressed in the CRN Site COLA.
A.4.4.2.1 Process Monitors (Radiological)
The process system continuously monitors selected lines containing or possibly containing radioactive effluents. The system's function is to warn personnel of increasing radiation levels, to give early warning of a system malfunction, and to record and control discharges of radioactive liquids and gases to the environment.
A.4.4.2.2 Area Radiation Monitors Area monitors are placed at specific locations in the plant.
A.4.4.2.3 Portable Monitors Portable radiation detection equipment consists of low-range and high-range instruments to measure gamma dose rates. Instruments for alpha, beta-gamma, and neutron radiation measurements are available. Sampling equipment is available to collect and analyze air samples. The Counting Room has appropriate equipment for isotopic analysis of sample media.
A.4.4.3 Process Monitors (Non-radiological)
The Control Room provides a central, protected location for placement of the necessary instrumentation to assess plant systems status, including reactor coolant system pressure and temperature, containment pressure and temperature, liquid levels, flow rates, fire detection equipment, and meteorological instrumentation.
A.4.4.4 Safety Parameter Display System (or equivalent)
The plant is equipped with the capability to display information required for a Safety Parameter Display System (SPDS) or an equivalent system.
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Appendix A A.4.4.5 Emergency Response Data System The Operations Duty Specialist (ODS) activates the Emergency Response Data System (ERDS), which transmits selected plant monitoring data to the NRC, within one hour of the declaration of an Alert or higher level emergency classification.
A.4.4.6 Fire Protection The plant's fire protection system provides extinguishing agents with the capability of extinguishing any single or probable combination of simultaneous fires that might occur. TVA controls the use of combustible materials.
A.4.4.7 Environment Facilities available for assessing the impact of plant operations on the environment include atmospheric monitoring stations, direct gamma radiation detectors, and water sampling capabilities. TVA maintains this equipment for use in the routine environmental radiological monitoring program and the equipment is available for use in the event of a radiological emergency condition.
The atmospheric monitoring network is divided into three subgroups. Local air monitors are located at or adjacent to the CRN Site Boundary in the directions of predominant wind flow.
Perimeter monitors are located farther from the plant in areas of relatively high population densities and/or in the direction of predominant air flow. Remote monitors (controls) are located at greater distances from the site.
Primary dosimeters are placed at selected sites around the plant. These dosimeters are located typically in each of the meteorological sectors at or near the CRN Site Boundary and at greater distances.
In addition to these facilities, established sampling points for milk, vegetation, soil, fish, and sediment are located in the vicinity of the plant. TVA may collect samples from these stations on a non-routine basis as needed.
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Appendix A A.4.5 EMERGENCY EQUIPMENT The CRN Site maintains supplies of emergency equipment located in designated storage locations. The CRN Site implements site-specific procedures to ensure required calibrations are carried out on a routine basis. Reference Appendix A, Attachment 2 for additional information regarding emergency equipment and supplies.
A.4.5.1 Emergency Communications Equipment Information regarding the CRN Site Emergency Communications Equipment is addressed in the CRN Site COLA.
A.4.5.2 First Aid and Medical Facilities A.4.5.2.1 Decontamination Facilities The site maintains supplies and equipment as needed to establish a temporary decontamination area for the purpose of gross radiological decontamination and injured person evaluation and stabilization. Equipment and materials for decontamination and first aid, including a stretcher, are available.
A.4.5.2.2 First Aid Stations and Supplies Emergency medical equipment is strategically located throughout the plant, with trauma kits and other specified equipment available for use by the Medical Emergency Response Team (MERT).
Emergency Medical Technicians (EMTs) provide first aid for injured individuals. Medical supplies and treatment for minor injuries are available. First aid treatment is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.
Rad Protection stores and controls potassium iodide (KI) tablets for onsite personnel. CRN-EPIPs provide usage information, including information addressing authorization for use and dispersal of tablets.
A.4.5.2.3 Receiving Hospitals and Supplies TVA maintains arrangements with local medical facilities to receive patients from the CRN Site.
A.4.5.2.4 Ambulance Service TVA maintains an ambulance, staffed in conjunction with the MERT, at the site. TVA also maintains arrangements for offsite ambulance assistance to the CRN Site.
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Appendix A A.4.6 ADDITIONAL LOCAL SUPPORT A.4.6.1 Fire TVA maintains arrangements for local firefighting support upon request. The senior offsite fire official responding to the CRN Site coordinates response activities with the TVA Incident Commander. The CRN Site is responsible for providing radiological protection and proper safety clearance in affected areas.
A.4.6.2 Law Enforcement TVA maintains agreements with local law enforcement agencies to provide law enforcement support when necessary.
A.4.6.3 Vendor Support If necessary, the Nuclear Steam Supply System (NSSS) vendor will be contacted by the Central Emergency Control Center (CECC) to provide assistance in the form of manpower, equipment, and technical backup. Other vendors will also be contacted if their assistance is needed.
A.4.7 ASSEMBLY/ACCOUNTABILITY ALARM TVA maintains warning signals to alert onsite personnel of hazards and the need for assembly or evacuation.
A.4.8 LOCAL RECOVERY CENTER The CRN Site has a Local Recovery Center (LRC) which is a pre-designated facility dedicated for use by offsite TVA and NRC personnel that may be assigned to the CRN Site for recovery operations. In addition, the LRC may be used by the NRC during the event as an area near the site for assessment and assistance and has the capability to communicate offsite. Personnel in the LRC have access to necessary drawings and documents. Meteorological information is available in the LRC. The LRC may serve as an alternate emergency response facility, as needed, and during an emergency, may be used as a staging location for personnel prior to dispatch to the CRN Site.
Personnel in the LRC have access to necessary drawings, manuals, procedures and documents. Meteorological information and dose rate calculations are available in the LRC. The LRC has telephone communications capabilities to enable personnel to communicate with the CECC and the CRN Site TSC. The LRC is able to send and receive data and document production / reproduction equipment is available.
The location, function, and capabilities of the LRC is addressed in the CRN Site COLA.
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Appendix A A.5 MAINTAINING EMERGENCY PREPAREDNESS A.5.1 RESPONSIBILITY FOR THE EMERGENCY PREPAREDNESS EFFORT The Site Vice President maintains overall authority and responsibility for radiological emergency response planning. The Director, Emergency Preparedness is assigned responsibility for coordinating emergency preparedness efforts, including activities related to the development of emergency plans and procedures and coordinating the plans and procedures with supporting organizations to ensure the overall effectiveness of the program.
A.5.2 PROCEDURES The CRN Site maintains a range of emergency plan implementing procedures (CRN-EPIPs) that provide instructions for implementing the emergency response measures described in the site Emergency Plan, Part 5B Section 16 provides a description of the CRN-EPIP document control, approval and revision processes.
A.5.3 INDEPENDENT REVIEWS OF EMERGENCY PREPAREDNESS TVAs independent Quality Assurance organization performs, or oversees the performance of, periodic independent audits of the emergency preparedness program consistent with the requirements of 10 CFR 50.54(t). The audits include, at a minimum, the following:
- The Emergency Plan.
- EPIPs and practices.
- The emergency preparedness training program.
- Readiness testing (e.g., drills and exercises).
- Emergency response facilities, equipment, and supplies.
- Interfaces with State and local government agencies.
- Required records and documentation.
TVAs independent Quality Assurance organization documents audit results and improvement recommendations and reports these results to the CRN Site and TVA management. TVA establishes and maintains the frequency of the periodic audits based on an assessment of performance as compared to performance indicators; however, the audit frequency is not less than once every 24 months. In addition, TVA conducts a program audit as soon as reasonably practicable after a change occurs in personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but no longer than twelve months after the change.
TVA makes those portions of the audits that address the adequacy of interfaces with State and local governments available to the affected governments.
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Appendix A A.6 ALERT AND NOTIFICATION SYSTEM The alert and notification system network consists of one or more alerting and notification systems. Various technologies may be employed as TVA and the affected State and local agencies assess and consider these technologies. The alert and notification system network is under the control of the State or local emergency management agencies. The systems are designed to provide alert signals and instructional messages to the population within EPZ of the CRN Site within 15 minutes of the decision to notify the public.
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Appendix A A.7 TRAINING AND DRILLS A.7.1 TRAINING PERSONNEL Personnel with specific duties and responsibilities in the CRN Site Radiological Emergency Preparedness (REP) program receive instruction in the performance of their duties and responsibilities in accordance with CRN Site training procedures, and as required in ESPA Part 5B Section 15.
A.7.2 DRILLS AND EXERCISES TVA conducts drills and exercises to develop and maintain the key skills that are required for emergency response. TVA may conduct the drills identified in ESPA Part 5B Section 14 individually or as part of a REP exercise.
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Appendix A A.8 EMERGENCY PLAN IMPLEMENTING PROCEDURES The range of actions needed to implement the contents of this Plan are found in the CRN-EPIPs, which, at a minimum, address the following topics:
- Emergency Classification
- Notifications Associated with Emergency Conditions
- Emergency Communications
- Protective Action Recommendations
- Activation of the Emergency Response Organization
- Staffing and Operation of Emergency Response Facilities
- Site Assembly, Accountability, and Evacuation
- Core Damage Assessment
- Radiation Protection Under Emergency Conditions
- Plume Tracking and Assessment of Off-site Radiological Conditions
- Respiratory Protection and Distribution of Radioprotective Drugs
- Personnel Monitoring
- Decontamination
- Obtaining and Analyzing High Activity Samples Under Emergency Conditions
- Emergency Media Relations
- Recovery and Reentry Additional plant procedures address various activities that are required to support the ongoing maintenance of the EP program. These supporting procedures are not included within the body of the EPIPs. These supporting procedures address, at a minimum, the following topics:
- Emergency Equipment and Communications Systems Inventory and Operational Tests
- Conduct of Emergency Drills and Exercises
- Emergency Plan Training
- Maintaining Emergency Preparedness A-21 Revision 1
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Appendix A Attachment 1 STATE MULTIJURISDICTIONAL RADIOLOGICAL EMERGENCY RESPONSE PLAN The State of Tennessee Multijurisdictional Radiological Emergency Response Plan is maintained in the CECC and the CRN Site TSC.
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Appendix A Attachment 2 EMERGENCY EQUIPMENT AND SUPPLIES TVA establishes and maintains inventories of emergency equipment and supplies for use by emergency response personnel in the emergency response facilities and by TVA off-site field monitoring teams. The actual inventories are based on the activities that occur in, or are dispatched from, each individual facility. Actual inventories are established in inventory lists in accordance with EPIPs. Emergency kit inventories typically include the following:
- Radiation survey instrument(s).
- Surface contamination control and survey supplies.
- Air sampling equipment and sampling media.
- Scaler(s) or other appropriate radio-analytical counting instrument(s).
- Protective clothing.
- Contamination control and decontamination supplies.
- Respiratory protection equipment.
- Radiological control posting and warning supplies.
- Personnel monitoring equipment (record and instantaneous reading dosimeters).
- Radioiodine blocking agent.
- Emergency lighting equipment.
- Appropriate maps.
- Computer equipment.
- Administrative and recordkeeping supplies.
- Plans, procedures, and drawings.
- Communications equipment.
- Batteries and other expendable supplies.
- First aid supplies (e.g., bandages, stretchers, splints, topical ointments).
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Appendix A Attachment 3 CROSS REFERENCE TO REGULATIONS AND GUIDANCE NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions 10 CFR 52.17(b)(1) N/A No known physical characteristics /
impediments to development of emergency plans.
10 CFR 52.17(b)(2)(i) N/A All (major features emergency plan) 10 CFR 52.17(b)(3) N/A Emergency Preparedness Inspections, Tests, Analysis and Acceptance Criteria (EP-ITAAC) 10 CFR 52.17(b)(4) N/A 16.5 10 CFR 50.72(a)(4) N/A A.4.4.5 10 CFR 50.72(c)(3) N/A 3.2, 6.4, 8.1.1, 8.2 10 CFR 50.47(b)(1) A.1.a 3.3, 3.3.24, 3.3.25, 3.3.26, 3.3.27, A.4.5.2, A.4.6 10 CFR 50 App E.IV.A A.1.b 2.3, 3.1, 3.2, 3.3, A.3 A.1.c Figure 3-1, Figure A.3-1, Figure A.3-2 A.1.d 3.2, A.3 A.1.e 3.2, 5.2, A.3 A.2.a N/A A.2.b N/A A.3 16.5 A.4 3.2, A.5.1 10 CFR 50.47(b)(2) B.1 3.2, A.3 10 CFR 50 App E.IV.A B.2 3.2, A.3.6.2 10 CFR 50 App E.IV.H B.3 3.2 A-24 Revision 1
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Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions B.4 3.2, A.3.6.2 B.5 3.1.1, 3.2, 3.3, Figure 3-1, A.3, Figure A.3-1, Figure A.3-2 B.6 Figure 3-1, Figure A.3-1, Figure A.3-2 B.7 3.2, A.3 B.7.a 3.3.23 B.7.b 13.0 B.7.c 3.2, A.3.6.1 B.7.d 3.3.1, 3.3.13, 7.0, 7.1, 7.2, 7.3, 7.4 B.8 3.3.26, A.4.6.3 B.9 Figure 2-1, 3.3.24, 12.2, 12.3, 12.4, A.4.5, A.4.6 10 CFR 50.47(b)(3) C.1.a 2.4 10 CFR 50 App E.IV.A C.1.b 2.4, 3.3.25 C.1.c 1.0, 6.0, 6.1, 6.2, 6.4, 6.7, 6.8, 8.1, 13.3, A.4.8 C.2.a N/A C.2.b 3.3.7, 5.2.3, 5.2.4 C.3 9.2.2, 9.2.3, A.4.3 C.4. 2.3, 3.3.24 - 3.3.26, 9.2, 12.4, 16.5, A.4.6 10 CFR 50.47(b)(4) D.1 4.1, 4.2, A.2 10 CFR 50 App E.IV.B D.2 A.2 D.3 N/A D.4 N/A A-25 Revision 1
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Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions 10 CFR 50.47(b)(5) E.1 5.0, 5.1, 5.2 (all), Figure 5-1 10 CFR 50 App E.IV.C E.2 3.3.5, 3.3.6, 5.0, 5.1, 5.2 (all), Figure 5-1 10 CFR 50 App E.IV.D E.3 5.0, 5.2 E.4 5.0, 5.2 (details described in EPIPs)
E.4.a 5.0, 5.2 (details described in EPIPs)
E.4.b 5.0, 5.2 (details described in EPIPs)
E.4.c 5.0, 5.2 (details described in EPIPs)
E.4.d 5.0, 5.2 (details described in EPIPs)
E.4.e 5.0, 5.2 (details described in EPIPs)
E.4.f 5.0, 5.2 (details described in EPIPs)
E.4.g 5.0, 5.2 (details described in EPIPs)
E.4.h 5.0, 5.2 (details described in EPIPs)
E.4.i 5.0, 5.2 (details described in EPIPs)
E.4.j 5.0, 5.2 (details described in EPIPs)
E.4.k 5.0, 5.2 (details described in EPIPs)
E.4.l 5.0, 5.2 (details described in EPIPs)
E.4.m 5.0, 5.2 (details described in EPIPs)
E.4.n 5.0, 5.2 (details described in EPIPs)
E.5 N/A E.6 8.5, A.6 E.7 7.1, 9.2.1 10 CFR 50.47(b)(6) F.1.a 3.2, 5.2, 6.0, 6.1, 6.2, 6.4, 6.7, A.3, A.4.5.1 A-26 Revision 1
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Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions 10 CFR 50.72(a)(3) F.1.b 3.3.4, 6.4, A.4.5.1 F.1.c 3.2, 6.4, A.4.5.1 F.1.d 6.0, 6.1, 6.2, 6.4, 6.7, A.4.5.1 F.1.e 6.5, 6.6, A.4.5.1 F.1.f 6.0, 6.4, A.4.5.1 F.2 6.0, 6.1, 6.2, 6.4, 6.8, A.4.5.1 F.3 6.0, 6.4, A.4.5.1 10 CFR 50.47(b)(7) G.1 7.0, 7.1, 7.2, 7.2.4, 7.5 10 CFR 50 App E.IV.D G.2 7.0, 7.1, 7.2, 7.2.4, 7.5 G.3.a 3.3.13, 7.0, 7.1, 7.2.1 - 7.2.4, 7.3, 7.4 G.3.b 7.3 G.4.a 3.3.13, 7.2.1 - 7.2.4 G.4.b 7.4 G.4.c 7.7 G.5 7.8 10 CFR 50.47(b)(8) H.1 8.0, 8.1, A.4, A.4.1, A.4.2 10 CFR 50 App E.IV.E H.2 Figure 8-1, 8.2 H.3 N/A H.4 Figure 3-1, 3.3, 6.0, 6.3, 6.5, 6.6 H.5 A.4.4 H.5.a 9.2.4 (all), A.4.4.1 H.5.b A.4.4.2 (all)
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Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions H.5.c A.4.4.3 H.5.d A.4.4.6 H.6.a 9.2.4 (all), A.4.4.1 H.6.b 11.0, Appendix A (Attachment 2)
H.6.c 9.2.3 H.7 9.2.2 H.8 9.2.4 (all), A.4.4.1 H.9 8.1.2, A.4.2 H.10 A.8 (EPIP list), Appendix A (Attachment 2)
H.11 Appendix A (Attachment 2)
H.12 8.2, 8.3 10 CFR 50.47(b)(9) I.1 9.0 (all)
I.2 9.1 I.3.a 9.2.5 I.3.b 9.2.5 I.4 9.2.4, 9.2.5 I.5 9.2.4 I.6 9.2.5 I.7 9.2.2 I.8 9.2.2 I.9 9.2.2 I.10 9.2.2, 9.2.5 A-28 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions I.11 N/A 10 CFR 50.47(b)(10) J.1.a 10.1, A.4.7 J.1.b 10.1, A.4.7 J.1.c 10.1, A.4.7 J.1.d 10.1, A.4.7 J.2 10.1, A.4.7 J.3 10.1 J.4 10.1 J.5 10.1, A.4.7 J.6.a 10.1, 11.0 (all)
J.6.b 10.1, 11.0 (all)
J.6.c 10.1, 11.0 (all)
J.7 10.3 J.8 ETE J.9 N/A J.10.a ETE J.10.b ETE J.10.c 8.5, A.6 J.10.d N/A J.10.e N/A J.10.f N/A J.10.g N/A A-29 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions J.10.h N/A J.10.i N/A J.10.j N/A J.10.k N/A J.10.l N/A J.10.m 10.3 J.11 N/A J.12 N/A 10 CFR 50.47(b)(11) K.1.a 12.0, 12.1, 12.2 (all), 12.4 K.1.b 12.0, 12.1, 12.2 (all), 12.4 K.1.c 12.0, 12.1, 12.2 (all), 12.4 K.1.d 12.0, 12.1, 12.2 (all), 12.4 K.1.e 12.0, 12.1, 12.2 (all), 12.4 K.1.f 12.0, 12.1, 12.2 (all), 12.4 K.1.g 12.0, 12.1, 12.2 (all), 12.4 K.2 11.0, Table 11-1, Table 11-2 K.3.a 11.0 K.3.b 11.0 K.4 N/A K.5.a 11.0, 12.1, 12.2.3, A.4.5.2.1 K.5.b 11.0, 12.1, 12.2.3, A.4.5.2.1 K.6.a 11.0 A-30 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions K.6.b 11.0 K.6.c 11.0 K.7 11.0, 12.2.3, A.4.5.2.1 10 CFR 50.47(b)(12) L.1 12.4 L.2 12.1, A.4.5.2.2 L.3 N/A L.4 12.3, A.4.5.2.4, 10 CFR 50.47(b)(13) M.1 13.1, Figure 13-1, 13.2 (all), 13.3, 13.4, A.4.8 10 CFR 50 App E.IV.H M.2 Figure 13-1, 13.2 (all)
M.3 13.1 M.4 9.2.5, 13.5 10 CFR 50.47(b)(14) N.1.a 14.2, A.7.2 N.1.b 14.2, A.7.2 N.2.a 14.1.7, A.7.2 N.2.b 14.1.6, A.7.2 N.2.c 14.1.1, A.7.2 N.2.d 14.1.2, A.7.2 N.2.e(1) 14.1.3, A.7.2 N.2.e(2) 14.1.4, A.7.2 N.3.a 14.3, A.7.2 N.3.b 14.3, A.7.2 N.3.c 14.3, A.7.2 A-31 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions N.3.d 14.3, A.7.2 N.3.e 14.3, A.7.2 N.3.f 14.4, A.7.2 N.4 14.4, A.7.2 N.5 14.4, A.7.2 10 CFR 50.47(b)(15) O.1 15.0, 15.1, 15.2, 15.3, A.7.1 10 CFR 50 App E.IV.F O.1.a 15.2, A.7.1 O.1.b N/A O.2 15.1, A.7.1 O.3 15.1, A.7.1 O.4.a 15.0, 15.1, A.7.1 O.4.b 15.0, 15.1, A.7.1 O.4.c 15.0, 15.1, A.7.1 O.4.d 15.0, 15.1, A.7.1 O.4.e 15.0, 15.1, A.7.1 O.4.f 15.0, 15.1, A.7.1 O.4.g 15.0, 15.1, A.7.1 O.4.h 15.0, 15.1, A.7.1 O.4.i 15.0, 15.1, A.7.1 O.4.j 15.0, 15.1, A.7.1 O.5 15.0, 15.1, 15.2, A.7.1 10 CFR 50.47(b)(16) P.1 15.3, A.7.1 A-32 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan (2-Mile EPZ)
Appendix A NUREG-0654, Rev. 1, Corresponding Early Site Permit Requirements Evaluation Criterion Application Emergency Plan Provisions 10 CFR 50 App E.IV P.2 A.5.1 10 CFR 50 App E.IV.G P.3 A.5.1 P.4 A.5.1, A.5.2 P.5 16.1, 16.2 (all)
P.6 Appendix A (Attachment 1)
P.7 9.2.1, A.8 P.8 Table of Contents (Generic Part), Table of Contents (Appendix A), Appendix A (Attachment 3)
P.9 16.4, A.5.3 P.10 16.2.2 A-33 Revision 1
Tennessee Valley Authority Clinch River Nuclear Site Early Site Permit Application Part 5B Emergency Plan (2-Mile EPZ)
Revision 1 Supplemental Information Evacuation Time Estimate Report Revision 0 September 2015
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate ABSTRACT The evacuation time estimate (ETE) detailed in this report is an analysis of the time required to evacuate the Plume Exposure Pathway Emergency Planning Zone (EPZ) for the Clinch River Nuclear (CRN) Site. The CRN Site is a proposed Small Modular Reactor (SMR) project on 1200 acres of land adjacent to the Clinch River arm of the Watts Bar Reservoir, south of the U.S. Department of Energy Oak Ridge Reservation (DOE/OR), within the City of Oak Ridge, in Roane County, Tennessee. The CRN Emergency Plan considers the unique plant design and margins to safety afforded by a SMR design, while maintaining emergency preparedness at appropriate levels to protect the health and safety of the public. For the proposed CRN Site, the EPZ is an area encompassing an approximate 2 mile radius around the proposed reactor center point location. NUREG/CR-7002, Criteria for Development of Evacuation Time Estimate Studies (NUREG/CR-7002), provides guidance for the development of ETEs. The guidance provided in NUREG/CR-7002 can be used to demonstrate compliance with the ETE analysis development required by the NRC in Section IV of Appendix E to Title 10 of the Code of Federal Regulation (CFR) Part 50 (10 CFR 50) and serves as a template for the development of this ETE study. Typically, the ETE is used to inform protective action decision-making and may also be used to assist offsite authorities in development of traffic management plans to support an evacuation. For purposes of the CRN Site Early Site Permit Application (ESPA), the ETE also serves to satisfy the requirements of 10 CFR 52.17(b)(1), which states that the site safety analysis report identify physical characteristics of the proposed site, such as egress limitations from the area surrounding the site, that could pose a significant impediment to the development of emergency plans and if physical impediments are identified, the application must identify measures that would, when implemented, mitigate or eliminate the significant impediment..
Consistent with guidance, this ETE has been developed to provide the time to evacuate 90 percent and 100 percent of the total population of the EPZ. The 90 percent ETE provides the evacuation times that would typically be used to support protective action recommendations and decision-making.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate TABLE OF CONTENTS ABSTRACT ................................................................................................................................... i TABLE OF CONTENTS ............................................................................................................... ii EXECUTIVE
SUMMARY
............................................................................................................ vii ACRONYMS AND ABBREVIATIONS ........................................................................................ xi PREFACE ................................................................................................................................... xii
1.0 INTRODUCTION
............................................................................................................... 1 1.1. Approach ....................................................................................................................... 7 1.2. Assumptions .................................................................................................................. 9 1.3. Scenario Development ................................................................................................ 11 1.4. Emergency Response Planning Areas........................................................................ 17 2.0 DEMAND ESTIMATION ................................................................................................. 18 2.1. Permanent Residents and Transient Population ......................................................... 18 2.2. Transit Dependent Permanent Residents ................................................................... 29 2.3. Special Facility Residents ........................................................................................... 32 2.4. Schools........................................................................................................................ 33 2.5. Other Demand Estimate Considerations ..................................................................... 33 2.6. Summary of Demand Estimation................................................................................. 40 3.0 ROADWAY CAPACITY .................................................................................................. 43 3.1. Roadway Characteristics............................................................................................. 43 3.2. Capacity Analysis ........................................................................................................ 49 3.3. Intersections Control ................................................................................................... 49 3.4. Adverse Weather......................................................................................................... 50 4.0 DEVELOPMENT OF EVACUTION TIMES ..................................................................... 52 4.1. Trip Generation Time .................................................................................................. 52 4.2. Evacuation Time Estimate Modeling ........................................................................... 71 4.3. Evacuation Time Estimates for the General Public ..................................................... 72 5.0 OTHER CONSIDERATIONS .......................................................................................... 75 5.1. Development of Traffic Control Plans.......................................................................... 75 5.2. Enhancements in Evacuation Time ............................................................................. 76 5.3. State and Local Review............................................................................................... 76 5.4. Reviews and Updates ................................................................................................. 77 5.5. Reception Centers and Congregate Care Centers ..................................................... 77 5.6. New Reactors .............................................................................................................. 77 5.7. Early Site Permits ........................................................................................................ 78 6.0 GLOSSARY .................................................................................................................... 79
7.0 REFERENCES
................................................................................................................ 81 ii Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate APPENDICES Appendix A Roadway Network Characteristics Appendix B Evacuation Time Estimate Review Criteria Checklist Appendix C Traffic Simulation Model Inputs and Outputs iii Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate LIST OF FIGURES Figure 1.1 CRN Site Vicinity Map Figure 1.2 Location of Roadway Impact Scenario Figure 2.1 Permanent Resident Population by Sector Figure 2.2 Peak Transient Population by Sector Figure 2.3 Transient Facilities Location Map Figure 2.4 Population Estimates for the Shadow Evacuation Area Figure 2.5 Roadway Network in the Vicinity of the CRN Site Figure 2.6 Network Demand Validation Figure 3.1 Evacuation Network Map Figure 3.2 Evacuation Network Map - Grid I Figure 3.3 Evacuation Network Map - Grid II Figure 3.4 Evacuation Network Map - Grid III Figure 4.1 Flow Chart of Events and Activities Preceding the Evacuation Trip Figure 4.2 Trip Generation Distributions Comparison (Daytime)
Figure 4.3 Trip Generation Distributions Comparison (Nighttime)
Figure 4.4 Trip Generation Distributions Comparison (Weekend)
Figure C.1 Mobilization and Evacuation Curves Figure C.2 Time Lapse Simulation graphics iv Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate LIST OF TABLES Table 1.1 Evacuation Time Estimate Summary Information Table 1.2 General Assumptions Table 1.3 Evacuation Scenarios Table 2.1 Permanent Resident Population By Sector Table 2.2 Permanent Resident Population and Evacuating Vehicles Table 2.3 Peak Transient Population By Sector Table 2.4 Peak Transient Population and Evacuating Vehicles Table 2.5 Summary of Transient Facility Populations Table 2.6 Summary of Transit Dependent Residents Table 2.7 Major Employers in the EPZ Table 2.8 Total Population Considered for Each Scenario Table 2.9 Total Vehicles Considered for Each Scenario Table 3.1 Free Flow Speed by Functional Class Table 3.2 Speed Reductions in Inclement Weather Table 3.3 Weather Capacity Factors Table 4.1 Trip Generation Evacuation Events Table 4.2 Trip Generation Evacuation Activities Table 4.3 Notification Time Distribution Table 4.4 Prepare to Leave Work/Facility Time Distribution Table 4.5 Travel to Home/Residence Time Distribution Table 4.6 Prepare to Leave to Home/Residence Time Distribution Table 4.7 Trip Generation Distributions Description Table 4.8 Trip Generation Distributions (Daytime)
Table 4.9 Trip Generation Distributions (Nighttime)
Table 4.10 Trip Generation Distributions (Weekend)
Table 4.11 Evacuation of Transit Dependent Individuals Table 4.12 ETEs for Special Facility Populations Table 4.13 ETEs for Evacuation of the General Public (90% of the Affected Population)
Table 4.14 ETEs for Evacuation of the General Public (100% of the Affected Population)
Table A.1 Node Input File Table A.2 Link Input File v Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table A.3 Intersection Control Type Counts Table A.4 Intersection Control Summaries Table A.5 Summary of Signalized Intersections Table B.1 Evacuation Time Estimate Review Criteria Checklist Table C.1 Loading Curves Table C.2 Data Input by Zone Table C.3 Destination Nodes and Capacities Table C.4 Exiting Number of Vehicles by Hour by Exiting Node Table C.5 Exiting Percentage of Vehicles by Hour by Exiting Node Table C.6 Network-Wide Travel Time (Minutes)
Table C.7 Total Vehicles Exiting the Network Table C.8 Average Speeds for Major Evacuation Routes (mph) vi Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate EXECUTIVE
SUMMARY
This report describes the analyses undertaken to develop evacuation time estimates (ETE) for the Clinch River Nuclear (CRN) Site, and the associated results. The Clinch River Property consists of 1200 acres adjacent to the Clinch River arm of the Watts Bar Reservoir, south of the U.S. Department of Energy Oak Ridge Reservation (DOE/OR), within the City of Oak Ridge, in Roane County, Tennessee that is proposed to be used as the location to construct and operate a Small Modular Reactor (SMR) project.
Part 5 of the Early Site Permit Application (ESPA) being submitted for the CRN Site includes two (2) Emergency Plans (Part 5A and Part 5B) for review by the NRC. Part 5A will address a site boundary plume exposure pathway Emergency Planning Zone (EPZ) and Part 5B addresses a 2-Mile plume exposure pathway EPZ. The final EPZ size will be determined at the time the Combined License Application (COLA) is submitted. For purposes of the CRN Site ESPA, the ETE serves to satisfy the requirements of 10 CFR 52.17(b)(1), which states that the site safety analysis report identify physical characteristics of the proposed site, such as egress limitations from the area surrounding the site, that could pose a significant impediment to the development of emergency plans and if physical impediments are identified, the application must identify measures that would, when implemented, mitigate or eliminate the significant impediment. This ETE did not identify physical characteristics of the proposed site that could pose a significant impediment to the development of emergency plans.
In the event the site boundary EPZ is selected for the CRN Site, the Tennessee Valley Authority (TVA) has proposed an exemption from the requirements to perform an ETE and an update to this ETE will not be necessary.
The Clinch River Emergency Plan considers the unique plant design and margins to safety afforded by a SMR design, while maintaining emergency preparedness at appropriate levels to protect the health and safety of the public. The ETE are calculations of the time necessary to evacuate the Plume Exposure Pathway Emergency Planning Zone (EPZ), which is an area encompassing an approximate 2 mile radius around the proposed reactor center point location.
The exact size and configuration of the EPZ surrounding the CRN Site was developed in relation to local emergency response needs and capabilities as they are affected by such conditions as demography, topography, land characteristics, access routes and jurisdictional vii Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate boundaries. Of particular interest in the development of CRN Site plume exposure pathway EPZ is the overlapping emergency planning zone for the DOE/OR.
Section IV of Appendix E to Title 10 of the Code of Federal Regulation (CFR) Part 50 (10 CFR
- 50) requires that an analysis of the time required to evacuate be provided for various sectors and distances within the EPZ for transient and permanent residents. Consistent with Supplement 3, Guidance for Protective Action Strategies, of NUREG-0654/FEMA-REP-1, Rev.
1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (NUREG-0654), the Protective Action Recommendation for an EPZ encompassing an area of approximately 2 miles surrounding the CRN Site would be consistent throughout the EPZ. Therefore, the use of various sectors and distances within the EPZ is not appropriate for the CRN Site and this ETE only considers an evacuation of the entire EPZ reflecting the effects of seasonal variations, day-of-the-week, and adverse weather conditions. Based on the data obtained from the 2010 U.S. Census, projected to 2015, there are 856 permanent residents within the EPZ of the proposed CRN Site.
The ETE is primarily used to inform protective action decision-making and may also be used to assist in development of traffic management plans to support an evacuation, if deemed necessary by offsite response organizations (OROs). The ETE is used as an information tool, and therefore, no minimum evacuation time must be achieved. The guidance in NUREG-0654 Evaluation Criterion J.10, provides additional information regarding the use of ETE results. ETE are used by OROs when making offsite protective action decisions. This report was prepared based on guidance provided in NUREG/CR-7002, Criteria for Development of Evacuation Time Estimate Studies (NUREG/CR-7002).
This report provides details on the process used for the development of ETEs for two population segments, including:
- 1. Permanent residents and transient population.
- 2. Transit dependent permanent residents.
There are no school populations located within the EPZ.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate This report also provides details on the development of the evacuation demand considered in the ETE, preparation activities associated with development of the ETE, and the use of traffic simulation modeling. Other considerations included in this ETE analysis include:
- A shadow evacuation extending to 15 miles from the CRN Site assumes that 20% of the public outside the boundary of the EPZ to a distance of 15 miles from the CRN Site would spontaneously evacuate.
- Lack of existing emergency preparedness programs and evacuation plans, including:
- The absence of existing registration programs for people with disabilities and those with access and functional needs who do not reside in special facilities.
- The absence of existing evacuation routes.
- The absence of existing traffic control plans.
- Verification of the future commitment of resources, such as buses and ambulances.
- Consideration of the evacuation tail.
- Future ETE updates related to a Combined License Application.
This report includes a discussion of INTEGRATION, the traffic simulation model used in performance of the ETE and a summary of the key inputs, assumptions, outputs, and computational process associated with the simulation. The INTEGRATION software is listed in the U.S. Department of Transportations (DOT) Evacuation Management Operations (EMO)
Modeling Assessment: Transportation Modeling Inventory, developed to support selection of an appropriate model for use in evacuation analyses (Reference 1).
NUREG/CR-7002 establishes the need to include a 20 percent shadow evacuation in the analysis. A shadow evacuation is defined as an evacuation of people from areas outside an officially declared evacuation zone. The shadow population is considered in this analysis to account for any effect of people from the EPZ boundary to 15 miles impeding the evacuation of those under evacuation orders. According to the 2010 U.S. Census data, projected to the year 2015, there are approximately 186,500 permanent residents within 15 miles of the proposed CRN Site.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate The EPZ is sparsely populated with no major commercial facilities. There are no schools, correctional facilities, licensed day care facilities, nursing home facilities or major retail facilities located in the EPZ.
To summarize the results of this ETE, Table 4.13 of this report depicts evacuation times for nine scenarios (the tenth scenario is for peak construction which is not considered) and provides evacuation times for 90% of the affected population. As shown in Table 4.13, the shortest evacuation time is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 40 minutes and the longest evacuation time is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 17 minutes.
Similarly, Table 4.14 depicts evacuation times for 100% of the affected population. As shown in Table 4.14, the shortest evacuation time is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 1 minute and the longest evacuation time is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 52 minutes.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate ACRONYMS AND ABBREVIATIONS AADT Annual Average Daily Traffic AASHTO American Association of State Highway and Transportation Officials ACP Access Control Point ANS Alert and Notification System CFR Code of Federal Regulation COLA Combined License Application CRN Clinch River Nuclear DBE Design Basis Event DOE/OR U.S. Department of Energy Oak Ridge Reservation DOT Department of Transportation EAS Emergency Alert System EMO Evacuation Management Operations EPZ Plume Exposure Pathway Emergency Planning Zone ER Environmental Report ERPA Emergency Response Planning Area ESP Early Site Permit ESPA Early Site Permit Application ETE Evacuation Time Estimate FEMA Federal Emergency Management Agency FHWA Federal Highway Administration GIS Geographic Information Systems HCM Highway Capacity Manual LOS Level of Service MOE Measures of Effectiveness O-D Origin-Destination ORO Offsite Response Organization SMR Small Modular Reactor TCP Traffic Control Point TEMA Tennessee Emergency Management Agency TVA Tennessee Valley Authority U.S. United States VTTI Virginia Tech Transportation Institute xi Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate PREFACE NUREG/CR-7002, Criteria for Development of Evacuation Time Estimate Studies (NUREG/CR-7002), provides guidance for the development of Evacuation Time Estimates (ETE). It also identifies the importance of using approved emergency response plans and existing traffic control information to reflect the expected response actions during an emergency.
This report describes the analyses undertaken to develop ETE for the populace located within the Plume Exposure Pathway Emergency Planning Zone (EPZ) of the Clinch River Nuclear (CRN) Site, and the associated results.
Section 1 provides an introduction to the ETE, describes the characteristics of the EPZ, establishes general assumptions, and identifies the evacuation scenarios evaluated in this analysis. Section 2 provides details considered in developing demand estimates for permanent residents and transients, transit dependent populations, special facilities, schools, special events and quantifying a shadow evacuation. Section 3 describes the approach for evaluating the roadway capacity and establishes values for use in adverse weather calculations. Section 4 discusses the process for developing trip generation times and provides details on information included in traffic simulation modeling. Section 5 identifies other considerations including the need for development of a traffic control plan, potential enhancements to the ETE, and State and local review. Appendix A of the document provides characteristics for the roadways in the roadway network and Appendix B includes ETE review criteria contained in Appendix B of NUREG/CR-7002.
The ETE is primarily used by State and local governments to inform protective action decision-making and may also be used to assist in the future development of traffic management plans to support an evacuation, if deemed necessary by offsite response organizations. The ETE is used as an informational tool, and therefore, no minimum evacuation time must be achieved.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate
1.0 INTRODUCTION
The Clinch River Nuclear (CRN) Site is the location of a proposed Small Modular Reactor (SMR) nuclear power plant project adjacent to the Clinch River arm of the Watts Bar Reservoir, south of the U.S. Department of Energy Oak Ridge Reservation (DOE/OR), within the City of Oak Ridge, in Roane County, Tennessee. To account for the possibility of an emergency at the CRN Site, a hypothetical, unplanned release of radioactive materials is considered. This report describes the analyses undertaken to develop evacuation time estimates (ETE) for the populace located within the EPZ of the proposed nuclear power plant site, and the associated results.
The ETE analysis is an emergency planning tool that assesses, in an organized and systematic fashion, the feasibility of taking protective measures for the population in the area surrounding a nuclear power plant. For purposes of the CRN Site ESPA, the ETE serves to satisfy the requirements of 10 CFR 52.17(b)(1), which states that the site safety analysis report identify physical characteristics of the proposed site, such as egress limitations from the area surrounding the site, that could pose a significant impediment to the development of emergency plans and if physical impediments are identified, the application must identify measures that would, when implemented, mitigate or eliminate the significant impediment.
The ETE also provides a tool for offsite response organizations (OROs) to use in preplanning as well as protective action decision making should a radiological release requiring offsite protective action decisions occur. The ETE may also be used to assist in development of future traffic management plans to support an evacuation, as deemed appropriate by OROs. The ETE is used as a decision-making tool, and therefore, no minimum evacuation time must be achieved.
Section IV of Appendix E to Title 10 of the Code of Federal Regulation (CFR) Part 50 (10 CFR
- 50) requires that an analysis of the time required to evacuate be provided for various sectors and distances within the EPZ for transient and permanent residents. Consistent with Supplement 3, Guidance for Protective Action Strategies, of NUREG-0654/FEMA-REP-1, Rev.
1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (NUREG-0654), the Protective Action Recommendation for an EPZ encompassing an area of approximately 2 miles surrounding the CRN Site is expected to be consistent throughout the EPZ. Therefore, the use of various sectors and distances within the EPZ is not appropriate for the CRN Site and this ETE only 1 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate considers an evacuation of the entire EPZ reflecting the effects of seasonal variations, day-of-the-week, and adverse weather conditions. This report was prepared considering the ETE guidance provided in NUREG/CR-7002, Criteria for Development of Evacuation Time Estimate Studies (NUREG/CR-7002).
Roane County is located in southeastern Tennessee, encompasses 395 square miles, and has a population of approximately 54,000 residents distributed between five incorporated municipalities and its unincorporated areas. Kingston, the County seat, is located approximately 7 miles west-southwest of the proposed CRN Site. The Clinch River surrounds the CRN Site to the east, south and west. The county boundary is closest to the CRN Site approximately 3 miles to the east of the CRN Site.
The CRN Site is a proposed SMR nuclear power plant site. The CRN Emergency Plan considers the unique plant design and margins to safety afforded by a SMR design, while maintaining emergency preparedness at appropriate levels to protect the health and safety of the public. For the proposed CRN Site, the EPZ is an area encompassing an approximate 2 mile radius around the proposed reactor center point location. The EPZ encompasses sparsely populated areas and a portion of the DOE/OR. No major employment areas of the DOE/OR lie within the EPZ.
According to the U.S. Census 2010 data, projected to the year 2015, there are 856 permanent residents within the EPZ of the CRN Site. According to the 2010 U.S. Census data, projected to the year 2015, there are approximately 186,500 permanent residents within 15 miles of the proposed CRN Site. The EPZ is sparsely populated with no major commercial facilities. There are no schools, correctional facilities, licensed day care facilities, nursing home facilities or major retail facilities located in the EPZ.
Interstate 40 (I-40), located in the southeastern portion of the EPZ, is the primary east-west traffic route in the vicinity of the proposed CRN Site. I-40 crosses the EPZ boundary approximately 2 miles east and 2 miles south-southwest of the proposed CRN Site. Tennessee State Route 58 (Highway 58), located in the northwestern portion of the EPZ, is the primary north-south traffic route in the vicinity of the proposed CRN Site. Highway 58 crosses the EPZ boundary approximately 2 miles west and 2 miles north-northwest of the proposed CRN Site.
Numerous local roads are found throughout the EPZ. Figure 1.1 illustrates the area surrounding 2 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate the proposed CRN Site and includes the roadway network, population centers, jurisdictional boundaries, and significant topographical features in the area.
Interstate 75 (I-75), although outside of the EPZ, is a major traffic route intersecting with I-40 approximately 7 miles east of the proposed CRN Site.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 1.1 CRN Site Vicinity Map 4 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate The traffic simulation model INTEGRATION, used in performance of this ETE study, is a microscopic traffic assignment and simulation software that is well-suited for performance of ETEs for nuclear power plants. The INTEGRATION software calculates a number of Measures of Effectiveness (MOEs), which are addressed by NUREG/CR-7002 and it is listed in the U.S.
Department of Transportations (DOT) Evacuation Management Operations (EMO) Modeling Assessment: Transportation Modeling Inventory, (Reference 1) developed to support selection of an appropriate model for use in evacuation analyses.
INTEGRATION performs traffic simulations by tracking the movement of individual vehicles every 1/10 of a second. The INTEGRATION model computes a number of MOEs, including the network efficiency. This model has been validated against state-of-the-art delay estimation procedures using queuing theory and shockwave analysis and against standard traffic flow theory and has been utilized for the evaluation of real-life applications.
The key parameters gathered on the roadway segments include the length of roadway segment, the number of lanes on each segment, type of roadway intersection control (stop sign, yield sign, etc.), lane striping (left turn only, shared through and right turn, etc.), free-flow speed, base saturation flow rate, jam density, and speed-at-capacity. Additional details regarding the traffic simulation model utilized in this study are included in Section 4.2.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 1.1 Evacuation Time Estimate Summary Information ETE Element Current ETE*
Permanent Residents Total EPZ permanent resident population 856 Vehicle ratio (people / evacuating vehicle) 1.7 Evacuating vehicles per household 1.3 Transit Dependent Population Total transit dependent population 35 Number of buses 3 Number of ambulances 2 Transient Population Average transient population 99 Peak Transient population 197 Special Facilities Total population 52 Number of buses 0 Number of ambulances 0 Schools Not Applicable Total population -
Total capacity -
Number of buses -
Capacity (each bus) -
Shadow Evacuation Percent Estimated 20%
Special Event Not Applicable Population -
Location -
Duration -
Other Elements Adverse Weather Summer - Rain Winter - Snow/Ice Evacuation Model INTEGRATION Scenarios 10 Assumptions See Table 1.2
- A previous ETE has not been performed for the proposed CRN Site.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 1.1. Approach A meeting regarding the development of the ETE was conducted at the Tennessee Emergency Management Agency (TEMA) in Knoxville, Tennessee on January 9, 2014 and was attended by representatives of state and local emergency management and law enforcement agencies, local elected officials and representatives from various state and local government agencies and private-sector support organizations. The purpose of the meeting was to present the process used for developing the ETE for the proposed CRN Site and outline associated data and information needs that would be used as inputs in the ETE analysis. The meeting included a detailed discussion of the ETE process including the methods used to collect data (roadway survey, telephone survey and data collection forms).
Following the meeting, a detailed field survey of the EPZ roadway network was conducted to validate existing mapping and to obtain characteristics of the primary roadways in the EPZ.
Roadway characteristics obtained during the field survey include:
- Number of lanes
- Lane width
- Intersection configuration
- Lane channelization and striping
- Geometrics (curves and lengths)
- Posted and actual speeds
- Abutting land use
- Traffic control devices
- Unusual characteristics The detailed field survey was video archived for reference purposes during subsequent development of the INTEGRATION model network.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate A random telephone survey of households within the EPZ and surrounding area to 10 miles from the CRN Site was conducted to interview a statistically representative sample of residents.
The telephone survey resulted in interviews with 604 households and was designed to obtain information related to household demographics and the commuting habits of residents. This information was used to identify factors affecting the evacuee trip generation time (mobilization time) as well as other data to be used in the ETE analyses, including average household size, vehicles per household, vehicle occupancy and an estimate of the number of transit-dependent residents. The mobilization time is the major component of the total ETE when the EPZ population density is low and there is minimal traffic congestion, as is the case for the CRN Site.
The telephone survey provides a statistical confidence interval of plus or minus 4% at the 95%
level of confidence and is a sound, documented basis for the trip generation times needed to develop the calculated ETEs.
NUREG/CR-7002 defines the transient population as tourists, shoppers, employees, etc., who do not reside within the EPZ and other people temporarily visiting the EPZ (Reference 4).
Hotel, motel, and campground occupancy rates peak during the summer months and during special events in the area. A survey of the transient facilities was conducted to obtain information regarding the number of transients and vehicles expected at these locations. The survey was designed to obtain information related to the number of units at each facility, average yearly occupancy, average number of persons per occupied unit and average number of vehicles per occupied unit. The survey was used to estimate peak attendance at transient facilities. There are no hotels/motels and 1 campground/RV park within the EPZ. This facility is addressed in greater detail in Section 2.1.2.
One special facility, the Kingston Academy, currently exists within the EPZ. The Kingston Academy is a Psychiatric Residential Treatment Facility with living quarters and a capacity of 52 children between the ages of 5 and 17. The facility provides residential treatment and day treatment services. Special facilities are addressed in Section 2.3.
Data related to major employers (more than 50 total employees) provided in the CRN Site Early Site Permit Application (ESPA) Environmental Report (ER) was evaluated for use in development of this ETE. Major employers within the EPZ are addressed in Section 2.5.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate There are no schools, correctional facilities, licensed day care facilities, nursing home facilities or major commercial or retail facilities located in the EPZ.
1.2. Assumptions According to NUREG/CR-7002, the planning basis for the ETE includes the assumption that a rapidly escalating emergency is underway, an evacuation is ordered promptly by emergency management officials and no early protective actions have been implemented (Reference 4).
A 2-mile EPZ is evaluated in this ETE analysis and is included among the regulatory exemptions requested in the CRN Site ESPA.
Development of potential exemptions for SMRs is based on various design and analysis considerations. Specifically, the SMR licensing basis events (or Design Basis Events, DBEs) are expected to have small and delayed source term releases that will result in predicted on-and off-site radiation doses significantly lower than those considered in the bases for existing nuclear power plant emergency planning requirements. For Beyond DBEs, analyses would need to conclude that the slow progression rate of postulated severe event scenarios provides sufficient time to initiate appropriate mitigating actions to protect the health and safety of the public.
The following table, Table 1.2, General Assumptions, provides assumptions that the NRC included in NUREG/CR-7002 and additional assumptions considered in development of the ETE, as appropriate for the CRN Site. The telephone survey discussed in Section 2.2 of this report provides information on vehicle usage. Those assumptions that are used exclusively within individual sections of this report are addressed and discussed in the applicable section.
Assumptions used, beyond those explicitly accepted by NRC in published guidance, are supported by available technical reports, telephone survey data, documented communications, and other sources. Scenario-specific assumptions are addressed in section 1.3 of this report.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 1.2 General Assumptions The ETE is measured from the time that the advisory to evacuate is issued to 1 the public within the EPZ (e.g., initial emergency alert system (EAS) broadcast.
Mobilization of the public begins after initial notification and includes all 2 preparation activities (time for commuters to leave work, time for commuters to travel home, time to prepare the house) 3 Evacuation time ends when the last vehicle has exited the EPZ.
Background traffic is on the roadway when initial notification occurs and stops 4 entering the EPZ upon establishment of Access Control Points at 90 minutes following the advisory to evacuate.
A 50% capacity is appropriate for buses used in the evacuation of the transit 5
dependent population.
Shadow evacuation of 20% of the public occurs from the outside boundary of 6
the EPZ to a distance of 15 miles from the CRN Site.
7 Permanent residents will evacuate using local roads.
All daytime scenarios assume 90% of the commuters are at work. All evening 8 scenarios assume 10% of the commuters are at work. All weekend scenarios assume 10% of the commuters are at work.
Telephone survey results indicate the following:
- The average household contains 2.2 persons.
9
- The average household has 2.2 vehicles.
- 1.3 vehicles/household would be used during an evacuation 10 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 1.3. Scenario Development As suggested in NUREG/CR-7002, the evacuation scenarios presented in Table 1.3, below, were modeled to reflect the effects of seasonal variations, day-of-the-week, adverse weather, special events, roadway impacts and the peak construction workforce at the proposed CRN site on the ETE (Reference 4). These scenarios were developed to identify combinations of variables and events to provide ETE under varying conditions to support protective action decisions and to provide a range of potential evacuation situations dependent on site-specific considerations.
Table 1.3 Evacuation Scenarios Scenario Season Day Time Weather 1 Summer Midweek Daytime Normal 2 Summer Midweek Daytime Adverse*
3 Summer Weekend Daytime Normal 4 Summer Midweek and Evening Normal Weekend 5 Winter Midweek Daytime Normal 6 Winter Midweek Daytime Adverse*
7 Winter Weekend Daytime Normal 8 Winter Midweek and Evening Normal Weekend 9 Roadway Midweek Daytime Normal Impact 10 Peak Midweek Daytime Normal Construction
- See Table 3.1 A description of each scenario used in the study is provided below.
Scenario # 1 - Summer Midweek Daytime (Normal Weather): This scenario represents a typical normal weather daytime period when permanent residents are generally dispersed within the EPZ performing daily activities and major work places are at typical daytime levels. This scenario includes assumptions that schools are closed and hotel and motel facilities are occupied at peak levels. The scenario assumes that 1/4 of the transients are in the EPZ for a single night and 3/4 are staying multiple nights. It is further assumed that 1/4 of the multiple 11 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate night transients remain in hotel rooms and/or campgrounds during the day and 3/4 are participating in recreational activities within the EPZ. It is further assumed that 1/2 of the 3/4 (3/8 of total transient population within the EPZ) will return to their lodging facilities to retrieve belongings.
Scenario # 2 - Summer Midweek Daytime (Adverse Weather): This scenario represents an adverse weather daytime period when permanent residents are generally dispersed within the EPZ performing daily activities and major work places are at typical daytime levels. This scenario includes assumptions that permanent residents will evacuate from their place of residence; schools are closed and hotel and motel facilities are occupied at peak levels. The scenario assumes that 1/4 of the transients are in the EPZ for a single night and 3/4 are staying multiple nights. Due to adverse weather, it is assumed that 1/2 of multiple night transients remain in hotel rooms and/or campgrounds and 1/2 are participating in recreational activities within the EPZ. Of the 1/2 that are participating in recreational activities within the EPZ, it is assumed that 1/2 (1/4 of total transient population within the EPZ) will return to their lodging facilities to retrieve belongings.
Scenario # 3 - Summer Weekend Daytime (Normal Weather): This scenario represents a typical normal weather weekend period when permanent residents are both at home and dispersed within the EPZ performing typical summer weekend activities. This scenario includes assumptions that permanent residents will evacuate from their place of residence; schools are closed and students are at home or with their families; work places are staffed at typical weekend levels and hotel and motel facilities are occupied at peak summer weekend levels.
The scenario assumes that 1/4 of the transients are in the EPZ for a single night and 3/4 are staying multiple nights. It is further assumed that 1/4 of the multiple night transients remain in hotel rooms and/or campgrounds during the day and 3/4 are participating in recreational activities within the EPZ. It is further assumed that 1/2 of the 3/4 (3/8 of total transient population within the EPZ) will return to their lodging facilities to retrieve belongings.
Scenario # 4 - Summer Midweek and Weekend Evening (Normal Weather): This scenario represents a typical normal weather midweek and weekend evening period when permanent residents are generally at home with fewer dispersed within the EPZ performing evening activities. This scenario includes assumptions that permanent residents will evacuate from their place of residence; schools are closed and students are at home; work places are staffed at 12 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate typical evening levels; hotel and motel facilities are occupied at peak summer levels and all transients are at their lodging facilities.
Scenario # 5 - Winter Midweek Daytime (Normal Weather): This scenario represents a typical normal weather weekday period during the winter when school is in session, permanent residents are generally dispersed within the EPZ performing daily activities and major work places are at typical daytime levels. This scenario includes assumptions that students will evacuate directly from the schools and hotel and motel facilities are occupied at 50% of the peak summertime levels. The scenario assumes that 1/4 of the transients are in the EPZ for a single night and 3/4 are staying multiple nights. It is further assumed that 1/4 of the multiple night transients remain in hotel rooms and/or campgrounds during the day and 3/4 are participating in recreational activities within the EPZ. It is further assumed that 1/2 of the 3/4 (3/8 of total transient population within the EPZ) will return to their lodging facilities to retrieve belongings.
Scenario # 6 - Winter Midweek Daytime (Adverse Weather): This scenario represents an adverse weather weekday period during the winter when school is in session, permanent residents are generally dispersed within the EPZ performing daily activities and major work places are at typical daytime levels. This scenario includes assumptions that students will evacuate directly from the schools; work places are fully staffed at typical daytime levels and hotel and motel facilities are occupied at average levels. The scenario assumes that 1/4 of the transients are in the EPZ for a single night and 3/4 are staying multiple nights. Due to adverse weather, it is assumed that 1/2 of multiple night transients remain in hotel rooms and/or campgrounds and 1/2 are participating in recreational activities within the EPZ. Of the 1/2 that are participating in recreational activities within the EPZ, it is assumed that 1/2 (1/4 of total transient population within the EPZ) will return to their lodging facilities to retrieve belongings.
Scenario # 7 - Winter Weekend Daytime (Normal Weather): This scenario reflects a typical normal weather winter weekend period when permanent residents are both at home and dispersed within the EPZ. This scenario includes assumptions that schools are closed and students are at home; work places are staffed at typical weekend levels; and hotel and motel facilities are occupied at average weekend levels. The scenario assumes that 1/4 of the transients are in the EPZ for a single night and 3/4 are staying multiple nights. It is further assumed that 1/4 of the multiple night transients remain in hotel rooms and/or campgrounds 13 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate during the day and 3/4 are participating in recreational activities within the EPZ. It is further assumed that 1/2 of the 3/4 (3/8 of total transient population within the EPZ) will return to their lodging facilities to retrieve belongings.
Scenario # 8 - Winter Midweek and Weekend Evening (Normal Weather): This scenario reflects a typical normal weather midweek and weekend evening period when permanent residents are home and the work force is at a nighttime level. This scenario includes assumptions that schools are closed and students are at home; work places are staffed at typical nighttime levels; and hotel and motel facilities are occupied at average winter levels and all transients are at their lodging facilities.
Scenario # 9 - Roadway Impact Summer Midweek Daytime (Normal Weather): The intent of this scenario is to represent a variety of conditions that may impact a roadway segment such as construction, flooding, vehicle accidents, etc. The roadway impact scenario assumes that during a summer midweek normal weather daytime scenario, one section of an eastbound lane of I-40 is shut down near the EPZ boundary, resulting in a reduction in capacity. All assumptions included in Scenario #1 are included in this scenario. This analysis is conducted to understand the potential impact of such an event and to support the development of a traffic control plan by identifying areas where OROs may want to consider additional emergency planning such as the pre-positioning of response vehicles (e.g., tow trucks). The ETE for this scenario is not typically used in protective action recommendations or decision-making.
Figure 1.2 illustrates the location of the roadway impact scenario.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 1.2 Location of Roadway Impact Scenario 15 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Scenario # 10 - Peak Construction Midweek Daytime (Normal): This scenario represents a typical normal weather midweek daytime period when the peak number of construction workers are on-site and permanent residents are generally dispersed within the EPZ performing daily activities and major work places are at typical daytime levels. Up to 2,700 construction workers would be required during the peak phase of construction activities for a Small Modular Reactor plant at the Site. Peak plant staff is expected to be 500 employees. Construction workers and plant staff are expected to commute because there are no provisions for housing at the Site. A site plan detailing road access to the Site has not been finalized. Therefore, it was assumed that driveway access to and from the Site would be along Bear Creek Road. This scenario includes assumptions that schools are closed and hotel and motel facilities are occupied at peak levels. Assumptions related to the transient population are identical to Scenario #1. The existing roadway system was used for this scenario and no roadway improvements were considered. According to the census data in the area, the overall permanent population increasing rate from 2015 to 2024 is estimated to be 2.64%. Permanent resident and shadow populations were extrapolated to 2024 for this scenario.
1.3.1. Staged and Keyhole Evacuation NUREG/CR-7002 addresses the use of staged and traditional keyhole evacuations when making protective action decisions. Evacuation research has shown that implementation of a staged evacuation can be more beneficial to the public health and safety than the traditional keyhole evacuation (Reference 2). However, NUREG/CR-7002 was developed considering an EPZ size of an approximately 10-mile radius, where the benefits of a staged and traditional keyhole evacuations may be realized, given site-specific characteristics.
In a typical (NUREG/CR-7002) staged evacuation, evacuation times for the 0-2 mile and the 2-5 mile portions of a 10-mile EPZ are calculated separately to support a staged evacuation protective action decision (i.e., evacuation of the 0-2 mile zone, followed by subsequent evacuation of the 2-5 mile zone). Because this ETE analysis for the CRN Site considers an EPZ encompassing an approximate 2 mile radius around the proposed reactor center point location, staged and traditional keyhole evacuations are not appropriate for the CRN Site and have not been considered in this analysis. Instead, this analysis considers an evacuation of the entire EPZ for each evacuation scenario. Based on the data obtained from the 2010 U.S.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Census, projected to 2015, there are 856 permanent residents within the EPZ of the proposed CRN site.
1.4. Emergency Response Planning Areas As described in NUREG/CR-7002, conduct of the ETE typically requires consideration of discreet planning areas within the EPZ, referred to as Emergency Response Planning Areas (ERPAs) (Reference 4). ERPAs are defined as local areas within the EPZ for which emergency response information is provided. The establishment of ERPAs within an EPZ enables protective action recommendations and decisions to be made at the ERPA level. With a 2-mile EPZ, during an emergency at the CRN Site, protective actions will be implemented consistently throughout the EPZ. For this reason, development of ERPA within the EPZ are not necessary and ERPA are not considered in this analysis. Based on the characteristics of the EPZ for the proposed CRN Site, ETEs were developed for the complete evacuation of the entire EPZ for each evacuation scenario considered.
The permanent resident and transient populations for the EPZ are discussed in Section 2 of this report.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 2.0 DEMAND ESTIMATION This section of the ETE report details the process for developing an estimate of the number of people to be evacuated from the EPZ. The demand estimation includes permanent residents, transients, individuals with special needs, and any other members of the public in the EPZ at the time an evacuation is ordered. The potential exists for counting individuals in more than one of these groups (i.e., EPZ resident may also be counted as an employee or transient). To avoid double-counting permanent residents, and as a result, overestimating the number of evacuating vehicles, the percent of permanent residents of the EPZ assumed to be at parks, shopping, places of employment or other locations within the EPZ is identified in appropriate sections of this ETE report. Demographic data obtained from the U.S. Census 2010 (projected to 2015), a random telephone survey of permanent residents in the EPZ and surrounding area, and assumptions detailed throughout this ETE report, have been used to estimate the number of people and vehicles considered in the ETE. Demand estimates for the following population groups have been considered separately and account for all of the public in the EPZ:
- Permanent Residents and Transient Population (with access to a vehicle during an evacuation).
- Transit Dependent Permanent Residents (without access to a vehicle or dependent on help from outside the home to evacuate).
- Special Facility Residents (Residents of or those confined to nursing homes, jails, assisted living centers, hospitals, etc.).
- Schools (Public and private educational facilities).
Estimates of the population and number of evacuating vehicles for each of these population groups have been developed separately and are described in the following sections.
2.1. Permanent Residents and Transient Population The permanent resident population has been estimated using Census block data obtained from the U.S. Census 2010 and is projected to 2015 for this analysis. To determine the permanent resident population, the block data was loaded directly into geographic information systems (GIS) software and the permanent resident population and number of households were 18 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate calculated based on polar coordinate representation (population rose). The EPZ permanent residents, by sector, is presented in Table 2.1. Table 2.1 includes residents in the 2 to EPZ Boundary to reflect those areas where the EPZ extends irregularly beyond a 2-mile radius. The EPZ permanent resident population, the number of households and the number of evacuating vehicles are presented in Table 2.2. The permanent resident population is illustrated by sector in Figure 2.1.
Table 2.1 Permanent Resident Population By Sector Distance Direction 2015 Population 1 N 0 1 NNE 0 1 NE 5 1 ENE 8 1 E 8 1 ESE 6 1 SE 8 1 SSE 7 1 S 13 1 SSW 13 1 SW 13 1 WSW 15 1 W 17 1 WNW 21 1 NW 19 1 NNW 0 2 N 0 2 NNE 0 2 NE 0 2 ENE 8 2 E 13 2 ESE 38 2 SE 41 19 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Distance Direction 2015 Population 2 SSE 58 2 S 28 2 SSW 30 2 SW 50 2 WSW 66 2 W 105 2 WNW 87 2 NW 24 2 NNW 1 2 to EPZ Boundary N 0 2 to EPZ Boundary NNE 0 2 to EPZ Boundary NE 0 2 to EPZ Boundary ENE 1 2 to EPZ Boundary E 4 2 to EPZ Boundary ESE 21 2 to EPZ Boundary SE 26 2 to EPZ Boundary SSE 9 2 to EPZ Boundary S 0 2 to EPZ Boundary SSW 3 2 to EPZ Boundary SW 4 2 to EPZ Boundary WSW 21 2 to EPZ Boundary W 57 2 to EPZ Boundary WNW 8 2 to EPZ Boundary NW 0 2 to EPZ Boundary NNW 0 TOTAL 856 20 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 2.2 Permanent Resident Population and Evacuating Vehicles EPZ Population Households* Evacuating Vehicles*
856 389 506
- Estimated assuming 2.2 persons per household and 1.3 evacuating vehicles per household as determined by the random telephone survey of households within the EPZ and surrounding area. This results in an estimate of 1.7 people per evacuating vehicle.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 2.1 Permanent Resident Population by Sector 22 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate The transient population is defined as those people temporarily visiting the area and includes tourists, shoppers and employees who work in the EPZ but do not reside in the EPZ.
Estimates of the size of the transient population were obtained and used to determine the associated number of evacuating vehicles. A listing of transient population facilities and special event data was obtained through a combination of internet research and questionnaires, and interviews with facility representatives. Data gathering surveys focused on acquiring the number of hotel/motel rooms and campsites at each transient facility within the EPZ; the typical number of guests in each hotel/motel room and campsite and the average number of vehicles per hotel/motel room/campsite. The number of transients at these facilities was estimated based on the information obtained.
The average EPZ household size of 2.2 persons per household was applied to the transient population to determine the number of transient units. Transients are assumed to evacuate at the same value as the EPZ population, 1.7 people per evacuating vehicle. Section 2.1.2 provides estimates of the peak transient population presented by facility type. The peak transient population is illustrated by sector in Figure 2.2.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 2.3 Peak Transient Population By Sector Distance Direction 2015 Population 1 N 0 1 NNE 0 1 NE 0 1 ENE 0 1 E 0 1 ESE 0 1 SE 0 1 SSE 0 1 S 197 1 SSW 0 1 SW 0 1 WSW 0 1 W 0 1 WNW 0 1 NW 0 1 NNW 0 2 N 0 2 NNE 0 2 NE 0 2 ENE 0 2 E 0 2 ESE 0 2 SE 0 2 SSE 0 2 S 0 2 SSW 0 2 SW 0 2 WSW 0 2 W 0 2 WNW 0 24 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Distance Direction 2015 Population 2 NW 0 2 NNW 0 2 to EPZ Boundary N 0 2 to EPZ Boundary NNE 0 2 to EPZ Boundary NE 0 2 to EPZ Boundary ENE 0 2 to EPZ Boundary E 0 2 to EPZ Boundary ESE 0 2 to EPZ Boundary SE 0 2 to EPZ Boundary SSE 0 2 to EPZ Boundary S 0 2 to EPZ Boundary SSW 0 2 to EPZ Boundary SW 0 2 to EPZ Boundary WSW 0 2 to EPZ Boundary W 0 2 to EPZ Boundary WNW 0 2 to EPZ Boundary NW 0 2 to EPZ Boundary NNW 0 TOTAL 197 Table 2.4 Peak Transient Population and Evacuating Vehicles Transient Population Evacuating Vehicles*
197 116
- Estimated assuming 1.7 persons per evacuating vehicle as determined by the random telephone survey of households within the EPZ and surrounding area.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 2.2 Peak Transient Population by Sector 26 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 2.1.1. Permanent Residents with Vehicles The estimated number of evacuating vehicles per household (1.3) was adapted from the results of the random telephone survey of the households in the EPZ and surrounding area. These data, along with the estimated number of households in the EPZ were used to calculate the number of evacuating vehicles provided in Table 2.1 in the following manner:
EV = Evacuating Vehicles HH = Household Evacuating Vehicles = HH x EV HH As an example, Evacuating Vehicles:
= 389 x 1.3 HH
= 506 Evacuating Vehicles The actual need for permanent resident vehicles is thereby less than the given estimate.
However, the estimate of permanent resident vehicles is not reduced to account for schoolchildren outside of the EPZ at the time of an evacuation.
2.1.2. Transient Population Transient population groups are defined as those people who are not permanent residents and who enter the EPZ for a specific purpose (camping, recreation, etc.). Transients may spend less than one day in the EPZ or they may stay overnight or longer at camping facilities, hotels and motels. The only transient facility in the EPZ identified during development of the ETE is a campground located approximately one mile south of the CRN Site. Based on information obtained from the facilitys website, the facility has approximately 90 campsites. This facility is discussed in greater detail below.
Hotels and Motels There are no hotels or motels that have been identified within the EPZ.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Campgrounds There is 1 campground/RV park within the EPZ. Soaring Eagle Campground is located approximately 1 mile south of the proposed CRN Site with approximately 90 campsites/RV parking spots. Figure 2.3 illustrates the location of the campground.
Figure 2.3 Transient Facilities Location Map This facility is assumed to be at capacity during the summer scenarios, including during the Smokin the Water 4th of July Celebration discussed in Section 2.5.1. Assuming 2.2 people per 28 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate campsite (equivalent to the EPZ persons per household), the peak attendance at the campground is estimated as 197 people evacuating in 116 vehicles (assuming 1.7 persons per evacuating vehicle). Based on the small permanent resident population within the EPZ and the relatively small transient population associated with this single facility, the impact of double counting any permanent EPZ residents that may be at this facility is minimal. Therefore, no permanent EPZ residents are assumed to be at this facility. A summary of the transient facility population is included in Table 2.5.
Table 2.5 Summary of Transient Facility Populations Distance Direction (miles)
Facility Municipality Campsites Population Vehicles (from CRN Site)
Soaring Eagle 1 South Lenoir City 90 197 116 Campground 2.2. Transit Dependent Permanent Residents Transit-dependent permanent residents are those residents within the EPZ who do not have access to a vehicle or are dependent on help from outside the home to evacuate.
Schoolchildren would typically be included as a segment of the transit dependent permanent resident population. However, as described in Section 2.4, there are no schools located within the EPZ. The estimated number of transit-dependent permanent residents was adapted from the results of the random telephone survey of the households in the EPZ and surrounding area.
In addition to households that do not own a vehicle, consideration was also given to those households with 1 or 2 vehicles identified by the telephone survey. Calculations related to households with 0, 1 or 2 vehicles available during an evacuation are described below.
0-Vehicle Households The telephone survey indicated that 2% of the households in the EPZ do not own a vehicle. As indicated in Table 2.2, there are an estimated 389 households located in the EPZ; resulting in approximately 8 households without access to a vehicle during an evacuation. The telephone survey also indicates that of those households with no vehicles available for evacuation, the average household size is 1.2 people per household. This translates to approximately 10 29 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate people (8 x 1.2) in 0-vehicle households that would not have access to a vehicle during an evacuation, assuming all households residents are home at the time an evacuation is ordered.
1-Vehicle Households The results of the telephone survey indicate that approximately 21.8% of the households in the EPZ have 1 vehicle. The telephone survey also indicated that 42% of households in the EPZ have a commuter and 26.4% of commuters would not return home prior to evacuating. The telephone survey also indicates that of those households with 1 vehicle available for evacuation, the average household size is 1.48 people per household. This results in approximately 10 households (389 X 0.218 x 0.42 x 0.264) or 5 people (10 x (1.48 - 1)) (considering the commuter is away with the vehicle) in 1-vehicle households would not have access to a vehicle during an evacuation.
2-Vehicle Households The results of the telephone survey indicate that approximately 43.8% of the households in the EPZ have 2 vehicles. The telephone survey also indicated that 42% of households in the EPZ have a commuter and 26.4% of commuters would not return home prior to evacuating. The telephone survey also indicates that of those households with 2 vehicles available for evacuation, the average household size is 2.18 people per household. This results in approximately 2 households (389 X 0.438 x (0.42 x 0.264)2) or 1 person (2 x (2.18 - 2))
(considering both commuters are away with both vehicles) in 2-vehicle households would not have access to a vehicle during an evacuation.
3 or More-Vehicle Households The telephone survey indicates that of those households with 3 or more vehicles available for evacuation, the average household size is 2.58 people per household. Because the average household size is less than the number of vehicles available to the household, it is assumed that households with 3 or more vehicles will always have a vehicle available at home for evacuation during an emergency.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Transit-Dependent Ridesharing As discussed in NUREG/CR-7002, it is recognized that a portion of the transit-dependent population will rideshare during an evacuation, leaving the area with friends, neighbors, or relatives, and it is acceptable to assume that up to 50 percent of residents without vehicles will rideshare (Reference 4). This value is based on results of a national telephone survey conducted of EPZ residents (Reference 2) which indicate more than 50 percent of residents would offer a ride to individuals waiting for transportation. Empirical data obtained from the widely studied Mississauga, Canada evacuation in 1979 (Reference 3) also supports a value of 50 percent. Roane County emergency management officials agreed that a value of 50 percent was acceptable for this study. As a result, it is estimated that 9 people in 0-, 1-, and 2-vehicle households will require transit assistance during an evacuation. The number of transit-dependent permanent residents in 0, 1, and 2-vehicle households in the EPZ is summarized in Table 2.6.
Homebound Special Needs Population A subset of transit dependent residents includes people with disabilities and those with access and functional needs that live independent of a special facility. During development of the ETE, attempts were made to obtain data from Roane County to determine the demand for transit resources to accommodate homebound special needs individuals. Information on households with residents dependent on specialized transportation, such as wheelchair vans or ambulances, could not be provided by Roane County. However, as described in NUREG/CR-7002, a recent telephone survey of residents living within EPZs in the U.S. found that 6% of respondents said they, or someone in their household, would need assistance to evacuate (Reference 4). NUREG/CR-7002 cited NUREG/CR-6953, Vol. II, SAND2007-4195P, Review of NUREG-0654, Supplement 3, Criteria for Protective Action Recommendations for Severe Accidents - Focus Groups and Telephone Survey, October 2008 (Reference 2), as the source of this information. Because of the absence of information related to households with residents dependent on specialized transportation, it is assumed that 85% of special needs individuals requiring transportation are ambulatory and capable of being transported via buses. It is further assumed that 10% of special needs individuals requiring transportation are wheelchair bound, not capable of walking short distances, and require transportation via wheelchair bus and 5% of special needs individuals requiring transportation are bedridden and require transportation via 31 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate ambulance. It is further assumed that there are no more than 1 special needs individuals per household.
Based on the total permanent resident population of 856 within the EPZ of the CRN Site, it is estimated that approximately 24 households in the EPZ would house a special needs individual requiring assistance during an evacuation. Based on the assumptions above that 85% of special needs individuals are ambulatory (21 persons) 10% are wheelchair bound (3 persons) and 5% are bedridden (2 persons) it is estimated that a total of 26 homebound special needs individuals will be evacuated. Because the locations of these individuals is unknown, it is estimated that 2 buses will service those individuals that are ambulatory. Additionally, 1 wheelchair bus will service the wheelchair bound individuals and 2 ambulances will service the bedridden individuals. The number of transit-dependent permanent residents in a special needs situation is summarized in Table 2.6.
2.3. Special Facility Residents Special facility residents are those who reside in special facilities and are dependent upon facility personnel or emergency medical services vehicles for transportation in an emergency.
This includes, but is not limited to, institutions such as hospitals, nursing homes, and correctional facilities. The presence of special facilities was researched during development of the ETE and it was determined that one facility, the Kingston Academy, currently exists within the EPZ.
The Kingston Academy is a Psychiatric Residential Treatment Facility with living quarters and a capacity of 52 children between the ages of 5 and 17. The facility provides residential treatment and day treatment services. For this ETE, it is assumed the facility is at 90% capacity when an evacuation is ordered and the facility is ready to evacuate 75 minutes (60 minutes to prepare +
15 minutes to load vehicles) after the order to evacuate is issued. This results in an evacuation of approximately 47 residents from this facility. Because of the type of facility, it is assumed that all residents of the Kingston Academy are ambulatory. The number of transit-dependent residents in special facilities is summarized in Table 2.6.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 2.6 Summary of Transit Dependent Residents Population Requiring Facility/Situation Evacuating Vehicles Evacuation Permanent Residents Without Access to Vehicle Buses 0-Vehicle Households 5 1-Vehicle Households 3 1 2-Vehicle Households 1 Homebound Special Needs Population (Including all members Various of household)
Ambulatory Patients 21 2 Buses Wheelchair Bound 3 1 Wheelchair Bus Bedridden 2 2 Ambulances Special Facility Residents Various Kingston Academy 47 3 facility vans 3 buses 1 wheelchair bus Total 82 2 ambulances 3 facility vans 2.4. Schools The presence of schools was researched during development of the ETE and it was determined that no schools currently exist within the EPZ.
2.5. Other Demand Estimate Considerations Demand estimates have also been considered for EPZ employees; a peak transients population during a special event just outside the EPZ; a shadow evacuation of 20% of the permanent resident population outside of the EPZ extending to 15 miles from the proposed CRN Site; and for background and pass through traffic within the EPZ. A summary of the shadow evacuation population and vehicles are included in Tables 2.8 and 2.9.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Employees In addition to the demand estimates for permanent resident and transient populations described above, demand estimates were also considered for people who work in the EPZ. There are two categories of people who work in the EPZ:
- 1. Those who live and work in the EPZ.
Those of the first category are already counted as part of the permanent resident population and previously accounted for in the demand estimate. In order to estimate the number of people who live outside the EPZ and commute to jobs within the EPZ, the presence of major employers in the vicinity of the CRN Site (50 or more employees) was researched during development of the ESPA ER and was evaluated for use in development of this ETE report. It was determined that two major employers exist within the EPZ. Information on the major employers is included in Table 2.7.
Table 2.7 Major Employers in the EPZ Distance Facility Employees Evacuating Direction Location Employees (miles) Name per Vehicle Vehicles*
Kingston 0.95 SW Kingston 150 1 36 Academy 0.75 WSW Duratek Kingston 300 1 71 Total 107
- Assume 90% of employees are at work when the order to evacuate is issued and 26.4% of employees evacuate directly from their place of employment (based on the results of the telephone survey). The remainder of the employees return home and are included in the permanent resident EPZ population.
2.5.1. Special Events Special events within an EPZ and can attract large numbers of transients for short periods of time. Special events could include Fourth of July celebrations, holiday parades, professional and amateur sporting events, or any number of activities that bring large populations into the 34 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate EPZ. These events frequently define the peak tourist population that is to be included in the ETE study (Reference 5).
Kingston, Tennessee hosts the Smokin the Water 4th of July Celebration (http://www.kingstonparks.com/Fourth%20of%20July%20-%20Smokin%20the%20Water.htm) each year with activities centered on the Kingston waterfront at Watts Bar Lake, approximately 10 miles west of the CRN Site and 8 miles outside the EPZ. The event is typically a one-day event, and features a floating parade, drag boat and raft races, children's activities, a classic car show, commercial and craft vendors and fireworks. It is assumed that this event will result in peak tourist populations at transient facilities within the EPZ. This peak tourist population is considered in the Scenario #4 described in Section 1.3. Based on the small permanent resident population in the EPZ, it is assumed that all permanent residents remain in the EPZ during this event and no reduction in permanent resident population is considered.
2.5.2. Shadow Evacuation A shadow evacuation is defined as an evacuation of people from areas outside an officially declared evacuation zone. The shadow population is considered in this analysis because the additional traffic generated has the potential to impede the evacuation of those in the EPZ under evacuation orders. Shadow evacuations were considered in developing the demand estimation because of the additional traffic typically generated during an evacuation and its potential to affect the ETE. Consistent with NRC guidance, a shadow evacuation of 20% of the permanent resident population was assumed to occur in areas outside of the EPZ for all cases extending to 15 miles from the CRN Site. Shadow population was determined based on U.S. Census 2010 data, projected to 2015. As noted in Table 1.2, the area outside the EPZ is assumed to have a shadow evacuation of 20% of the permanent resident population.
According to the Census data, projected to 2015, there are 186,500 permanent residents living within 15 miles of the CRN Site. It is assumed that the trip generation times for the shadow evacuation onto the roadway network is consistent with the trip generation times for the permanent resident population within the EPZ.
Figure 2.4 illustrates the permanent resident population by sector, at 1-mile increments from the EPZ boundary to 15 miles from the CRN Site.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 2.4 Population Estimates for the Shadow Evacuation Area 2.5.3. Background and Pass-Through Traffic Background and pass-through traffic will exist within the EPZ at the time an order to evacuate is issued. Background traffic is that traffic on the roadways when the initial notification to evacuate occurs and consists of both permanent residents and transients. Pass-through traffic includes 36 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate vehicles that enter the EPZ roadway network and exit the EPZ prior to the establishment of Access Control Points (ACPs).
QUEENSOD, software developed by Virginia Tech Transportation Institute (VTTI), was used to estimate the background and pass-through traffic. Because origin-destination (O-D) demand data is not readily available and difficult to obtain unless a large scale O-D survey is conducted, a method is needed to estimate demand by readily available data, such as traffic count data.
QUEENSOD is a model for estimating origin-destination traffic demands based on observed link traffic flows, observed link turning movement counts, link travel times and, potentially, additional information on drivers route choices. QUEENSOD iteratively minimizes errors between observed link volumes to estimated link flow using Least Relative Error model and generates an O-D matrix.
Pass-through traffic, used as input data in the ETE simulations, was determined based on the latest published traffic statistics, provided by the Tennessee Department of Transportation (http://www.tdot.state.tn.us/traffichistory). Annual Average Daily Traffic (AADT) on road sections of the State Highways and Local Federal-Aid roads are included on each of the major roadways within the EPZ. The count station, or specific location on a roadway where traffic count surveys are conducted, and the roadway network in the vicinity of the CRN Site are shown in Figure 2.3.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 2.5 Roadway Network in the Vicinity of the CRN Site 38 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate To validate the results of QUEENSOD, the output of the QUEENSOD, the O-D matrix, is used in INTEGRATION as input demand file. The simulation is then run and the link traffic counts are recorded and calibrated against the observed traffic count data. The figure below shows the relationship between the observed link volumes versus the simulation volume. As evidenced by the following figure, the results from QUEENSOD accurately replicate the known network demands. The coefficient of determination R2 (a statistical measure of how close the data are to the fitted regression line) is very close to 1.
Figure 2.6 Network Demand Validation The background and pass-through traffic volume is estimated, and the calibration verified, for each scenario with consideration given to the effects of seasonal variations, day-of-the-week, adverse weather and other factors.
It is assumed that ACPs would be staffed within approximately 90 minutes of the advisory to evacuate. Activation of ACPs prior to 90 minutes could delay commuters returning from areas outside of the EPZ. Therefore, for purposes of this analysis, it is assumed that ACPs will be 39 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate established at 90 minutes following the advisory to evacuate. It is also assumed that no vehicles will enter the EPZ after ACPs have been established. The establishment of ACPs at 90 minutes following the advisory to evacuate has been confirmed with OROs.
From the time an evacuation order is issued until 90 minutes after the order is issued, background traffic begins to diminish as evacuating traffic begins to exit the EPZ and the establishment of ACPs prevent inbound traffic from entering the EPZ. The evacuating traffic begins to increase at the rate of the time distributions related to the trip generation times (see section 4.1). The background and pass-through traffic stops entering the EPZ 90 minutes after the order to evacuate is issued.
2.6. Summary of Demand Estimation A total of 10 Scenarios were evaluated for an evacuation of the full EPZ. As previously described, the use of various sectors and distances within the EPZ is not appropriate for the CRN Site and this ETE only considers an evacuation of the entire EPZ reflecting the effects of seasonal variations, day-of-the-week, and adverse weather conditions resulting in a total of 10 unique evacuation cases. Each scenario results in a specific population to be evacuated. Table 2.8 provides a summary of the total populations used in the analysis for each scenario for an evacuation of the EPZ. Table 2.9 provides a summary of the total number of vehicles, by population group (permanent residents, transients, transit dependent residents, shadow population, background and pass-through), for each scenario for an evacuation of the EPZ and represents the input values used in the traffic simulation modeling.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 2.8 Total Population Considered for Each Scenario Transit Dependent Permanent Transient Special Major Shadow Scenario Permanent Total Population Residents Population Facilities Employers Population Residents 1 856 185 35 47 107 37,126 38,356 2 856 173 35 47 107 37,126 38,344 3 856 185 35 47 12 37,126 38,261 4 856 197 35 47 12 37,126 38,273 5 856 92 35 47 107 37,126 38,263 6 856 87 35 47 107 37,126 38,258 7 856 92 35 47 12 37,126 38,168 8 856 99 35 47 12 37,126 38,175 9 856 185 35 47 107 37,126 38,356 10* 879 190 128 47 2,810 38,091 42,053
- Peak Construction - Permanent Resident population and Shadow population have been extrapolated to the Year 2024, which is when the construction workforce will be at its peak. Major employer data includes projected construction employees at the CRN Site.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 2.9 Total Vehicles Considered for Each Scenario Permanent Transit Dependent Background and Transient Major Shadow Scenario Resident Permanent Schools Pass-through Total Vehicles Vehicles Employers Population Vehicles Resident Vehicles Traffic 1 658 109 6 0 107 21,206 45,069 67,155 2 658 102 6 0 107 22,246 45,069 68,188 3 658 109 6 0 12 21,985 36,055 58,825 4 658 116 6 0 12 21,985 22,535 45,312 5 658 54 6 0 107 22,247 45,069 68,141 6 658 51 6 0 107 22,246 45,069 68,137 7 658 54 6 0 12 21,985 36,055 58,770 8 658 58 6 0 12 21,985 22,535 45,254 9 658 109 6 0 107 22,246 45,069 68,195 10* 675 112 7 0 2,810 22,820 46,241 72,665
- Peak Construction - Permanent Resident population and Shadow population have been extrapolated to the Year 2024, which is when the construction workforce will be at its peak. Major employer data includes projected construction employees at the CRN Site.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 3.0 ROADWAY CAPACITY In conjunction with the development of the traffic network in the vicinity of the CRN Site, an estimate of roadway capacity is required. Roadway capacity is defined as the maximum rate at which vehicles can be expected to traverse a section of roadway during a given time period under prevailing roadway, traffic, weather, and control conditions. The capacity analysis in this study has been performed using the application of processes and equations established in the U.S. Department of Transportations Highway Capacity Manual (HCM) (Reference 6). The (LOS), as defined in the HCM, provides a quality measure of the traffic operational conditions of a roadway and is designated as A for free flow operating conditions through F for congested operating conditions.
The roadway network in the vicinity of the CRN Site consists of the following three primary categories of roads:
- 1. Two-lane Local Roads - Various local and residential streets are located within the city limits of Oak Ridge and Roane County.
- 2. State Roads (Highway 58) - The portion of Highway 58 traversing the EPZ begins at an interchange with I-40 west-southwest of the CRN Site, then heads northeast, crossing the EPZ boundary 2 miles west of the CRN Site. Highway 58 continues northeast, before turning north and exiting the EPZ, 2 miles north-northwest of the CRN Site.
- 3. Freeways (I-40) - I-40 is the primary east-west route through the EPZ and crosses the EPZ boundary 2 miles east and 2 miles south-southwest of the CRN Site.
The following sections discuss the methods used in this study to determine roadway capacity.
3.1. Roadway Characteristics Roadway characteristics were obtained from an ArcGIS network file, which is imbedded in the raw calibrated data obtained from the data provider. Roadway characteristics, such as number of lanes, lengths, and free flow speed were extracted from the network file and exported to simulation input files. Table 3.1 provides the definition of free flow speed based on functional class. There are six functional classes in the CRN Site area according to the definition of the roadway databases. Speed at capacity and jam density were then designed according to 43 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate suggestions from the HCM. Based on field surveys, such roadway characteristics were further adjusted and calibrated to reflect real situations. The roadways included in the ETE analysis are primarily functional class 2 to 5 in the vicinity of the CRN Site.
Table 3.1 Free Flow Speed by Functional Class Function Free Flow Speed at Capacity Capacity Jam Density Class Speed (mph) (mph) (Veh/Hour/Lane) (Veh/Mile/Lane) 1 80 65 2,400 240 2 65 50 2,400 240 3 55 45 2,300 240 4 45 35 2,250 240 5 30 25 2,100 240 6 20 15 1,900 240 Figures 3.1 through 3.4 illustrate the roadway system, including links and nodes used in the analysis. A link is defined as a segment of roadway between two nodes. A node is an identification designator used to connect links in a roadway network model or to apply input data onto the network. Nodes are at intersections, ramps, etc., and contain characteristics such as traffic control and may be used as input points to assign loading of vehicles. Links are identified using blue text and nodes are identified as boxes with accompanying black text identifiers in Figures 3.1 through 3.4.
Characteristics for the roadways in the roadway network, including nodes, links and loading input information are included in Appendix A.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 3.1 Evacuation Network Map 45 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 3.2 Evacuation Network Map - Grid I 46 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 3.3 Evacuation Network Map - Grid II 47 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 3.4 Evacuation Network Map - Grid III 48 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 3.2. Capacity Analysis Although the majority of the parameters for the road network that are input variables for the simulation are imported from the GIS database providers, local adjustments were conducted to ensure the accuracy of variables. The principles used for adjusting the variables are based on the HCM and the Green Book (A Policy on Geometric Design of Highways and Streets from AASHTO) (Reference 7).
The capacity of a road, according to the HCM, is the maximum sustainable hourly flow rate at which vehicles can reasonably traverse a point during a given time period under prevailing roadway, traffic, and control conditions (Reference 6).
According to the HCM, the factors affecting capacity of a roadway include design speed, number of lanes, the width of the lanes, shoulder, geometrical features (horizontal and vertical curves), traffic compositions as well as some other environment factors, such as weather, visual obstruction of the roadway, etc (Reference 6). These factors need to be incorporated into the simulation environment such that the simulation will be able to reflect the real traffic status, especially during the process of evacuation when congestion is possible in the network.
The capacity of the roadway is defined according to the recommendations by the HCM. The roads in the vicinity of the CRN Site are divided into the six functional classes based on the features of the roads, including hierarchy in the network, traffic load, serving environment, design speed, etc. The capacity of each class is defined in Table 3.1. The capacity in Table 3.1 is the description of network under perfect traffic conditions. As described in Section 3.4, a reduction in capacity is considered for ETE scenarios 2 and 6, considering adverse weather conditions.
3.3. Intersections Control Similar to the roadway capacity, intersection capacity is determined by multiple factors such as roadway geometrics, lane width, and number of lanes, etc. In addition, because intersections are the meeting point of two or more roads and they are usually controlled by traffic lights or other traffic control methodologies (stop signs or yield signs), the capacity at intersections will also be affected by the cycle length of the traffic signal, green time, turning movements, the 49 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate conflicting traffic, and other factors. It is important to reflect the prevailing intersection control treatments in the simulation such that the real traffic conditions should be replicated.
The underlying rules and parameters adopted by INTEGRATION at intersections, such as left and right turn gap acceptance, acceleration rate, discharge headway, and driver behavior during yellow light et al., are constructed in accordance with the recommendations from the HCM and are calibrated in-field.
The intersection traffic control data in the CRN Site area were obtained from two major sources.
Traffic signal timing data, including cycle length and phases, were requested from local town or county traffic agencies. Field survey data provided supplemental information for certain intersections. Stop signs and yield signs controlled intersections are identified from Google street view images. Data are then coded into an input file for INTEGRATION and are calibrated to field observations in terms of travel speeds and counts. Because the data obtained from local transportation agency is incomplete, estimation of cycle lengths and split of the signal is conducted based on the locations of the intersections where the signal data are not available.
The rules for estimation are based on geographic locations and road class resemblance. A similar traffic signal timing plan at an adjacent intersection of the same road class in the area was adopted for intersections where the data are not available. Because it is not uncommon for traffic control personnel to direct traffic and override the existing traffic signal plans resulting in improvement in the capacity of the intersections during an evacuation, the simulation optimizes the cycle lengths and offset times at a frequency of 5 minutes.
Characteristics for the intersections, including control summaries and signal files, are included in Appendix A.
3.4. Adverse Weather According to the HCM, during adverse weather the capacity and free flow speed of the roadway will be impaired (Reference 6). Table 3.2 illustrates the capacity drop and free flow speed reduction on freeways suggested by research conducted during previous studies.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 3.2 Speed Reductions in Inclement Weather Percent Percent Capacity Condition Speed Reduction Reduction Heavy Rain 10% - 18% 5% - 17%
Heavy Snow/Ice 20% - 28% 20% - 35%
The reduction in capacity and speed is calculated based on several factors including pavement condition, terrain, roadway functional class, and other factors. In accordance with the guidance presented in NUREG/CR-7002, the following roadway capacity and speed reduction factors were adopted for use in Scenarios 2 and 6, respectively (Reference 4). The values in Table 3.3 for heavy rain and snow are derived from Chapter 22 of the HCM, Exhibit 22-7 and the Federal Highway Administration (FHWA) study, Identifying and Assessing Key Weather-Related Parameters and Their Impacts on Traffic Operations Using Simulation (Reference 8).
Table 3.3 Weather Capacity Factors Scenario Season Weather Condition Roadway Capacity Speed 2 Summer Heavy Rain 90% 85%
6 Winter Heavy Snow/Ice 85% 65%
Based on the location of Clinch River and data obtained from NOAA (http://www.srh.noaa.gov/mrx/?n=oqtclimate) indicating average annual snowfall of 6.6 inches and 3 days per year with greater than 1 of snow, the winter adverse weather scenario (Scenario 6) considers ice as the limiting winter adverse weather condition and there is no effect on mobilization based on the need for snow removal from roadways or driveways.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 4.0 DEVELOPMENT OF EVACUTION TIMES Evacuation times are estimated for 90% and 100% of the evacuating vehicles to exit the EPZ boundary. A total of 10 scenarios were simulated in various weather, season, time, and network conditions to reflect the traffic conditions when the evacuation order is issued. Development of the evacuation times considered preparation activities, including the time to receive the notification and time to prepare to evacuate.
4.1. Trip Generation Time A random telephone survey of households within the EPZ was used to identify factors affecting the evacuee trip generation time (mobilization time) as well as other data to be used in the ETE analyses. The mobilization time is the major component of the total ETE when the EPZ population density is low and there is minimal traffic congestion, as is the case for the CRN Site.
The telephone survey provides a sound, documented basis for the trip generation times needed to develop the calculated ETEs.
With respect to trip generation time, the telephone survey was used to obtain data related to whether or not commuters would return home or evacuate directly from work; how long it would take commuters to travel home; and how long it would take to complete preparations at home and at work prior to evacuation. The data obtained from the telephone survey related to trip generation time is summarized in Tables 4.4, 4.5, and 4.6.
The evacuation trips consists of a sequence of events and activities. Each event (other than the notification alert) occurs at an instant of time, while activities are accomplished in series or parallel, over a period of time. The relevant events associated with the public's preparation for the evacuation trip are presented in Table 4.1. One or more activities are associated with each sequence of events as shown in Table 4.2.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.1 Trip Generation Evacuation Events Event Description 1 Notification to public 2 Awareness of incident 3 Leave work/facility 4 Arrive home/residence 5 Leave to evacuate Table 4.2 Trip Generation Evacuation Activities Activity Description Event Sequence 1 Receive notification 12 2 Prepare to leave work/facility 23 3 Travel home/residence 34 4 Prepare to leave to evacuate 2,4 5 The Trip Generation Time (the total elapsed time from Event 1 to 5) is dependent on the scenario and will vary from one household to another. Factors affecting the trip generation time include, but are not limited to the following:
- A commuter may or may not return home prior to evacuating.
- Households with a vehicle available for evacuation may or may not wait for a commuter to return home prior to evacuating.
- Transients within the EPZ may evacuate immediately without returning to their residence (With respect to transients, residence refers to their hotel, motel or campground.).
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate The flow chart included as Figure 4.1 indicates the relationship of events and activities preceding the evacuation trip.
Figure 4.1 Flow Chart of Events and Activities Preceding the Evacuation Trip 54 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Estimated Time Distributions of Activities Preceding the Evacuation Trip The time distribution of an event is obtained by "summing" the time distributions of all prior contributing activities.
NUREG-0654/FEMA-REP-1 Appendix 3 (as amended by Supplement 4), 44 CFR 350.5(a), and Section V, Part A of the Federal Emergency Management Agency (FEMA) Radiological Emergency Preparedness (REP) Program Manual (FEMA P-1028) (Reference 9), discuss Alert and Notification System (ANS) design objectives. The minimum acceptable design objectives for coverage by an ANS is the capability for providing an alert signal and beginning an informational or instructional message to the population in the EPZ within 15 minutes and providing protective action recommendations, if appropriate. The coverage of essentially 100%
of the population in the EPZ who may not have received the initial notification must occur within 45 minutes. Based on the regulatory requirements and guidance in FEMA P-1028, the notification distribution used in this analysis is provided in Table 4.3.
Table 4.3 Notification Time Distribution Elapsed Time Percentage of (Minutes) Population Notified 0 0%
5 7%
10 13%
15 27%
20 47%
25 66%
30 87%
35 92%
40 97%
45 100%
It is assumed following notification and evacuation order, most businesses within the EPZ will shut down and most employees would leave work quickly and that residents dispersed within the EPZ performing daily activities will travel home. Table 4.4 shows the preparation time distribution to leave work/facility (Activity 2) from data obtained by those households that 55 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate responded to the telephone survey. This distribution is applicable for all commuters (those going home prior to evacuating, those evacuating directly from work, or those living outside the EPZ) and for residents to leave stores, restaurant, parks, and other locations within the EPZ.
Notification of the transient population is assumed to occur at the same time distribution as permanent residents. Those transients in campgrounds within the EPZ will receive an alert via the ANS.
Table 4.4 Prepare to Leave Work/Facility Time Distribution Elapsed Time Cumulative (Minutes) Percentage 0 0%
10 79.6%
15 86.1%
20 91.2%
30 96.5%
40 97.3%
50 98.4%
60 98.9%
120 99.5%
180 99.7%
240 100.0%
The time distribution to travel home (Activity 3) for commuters/residents after leaving work/facility was obtained from those who responded to the telephone survey and is provided in Table 4.5. This distribution is applicable for transients going back to residence to begin the evacuation trip.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.5 Travel to Home/Residence Time Distribution Elapsed Time Cumulative (Minutes) Percentage 0 0.0%
5 11.5%
10 24.9%
15 39.1%
20 51.7%
25 60.1%
30 78.3%
35 82.0%
40 89.0%
45 93.3%
50 94.6%
55 94.6%
60 97.1%
75 97.9%
90 99.2%
105 99.2%
120 99.5%
150 99.5%
180 99.5%
210 99.7%
240 99.7%
300 100.0%
The preparation time distribution for households to leave home (Activity 4) to begin the evacuation trip was obtained from those who responded to the telephone survey, under different time scenarios (daytime, nighttime, and weekend) and is included in Table 4.6. This distribution is also applicable for transients preparing at their residence to begin the evacuation trip.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.6 Prepare to Leave Home/Residence Time Distribution Elapsed Time Cumulative Percentage (Minutes)
Daytime Night time Weekends 0 0.0% 0.0% 0.0%
15 40.9% 38.4% 39.7%
30 59.4% 57.9% 58.9%
45 81.5% 81.1% 81.3%
60 89.4% 88.6% 89.1%
75 94.4% 93.2% 94.0%
90 94.5% 93.7% 94.2%
105 95.0% 94.7% 95.2%
120 96.5% 96.2% 96.7%
135 98.5% 98.2% 98.8%
150 98.7% 98.3% 99.0%
165 98.8% 98.7% 99.0%
180 99.2% 98.8% 99.2%
195 99.3% 99.0% 99.3%
210 99.3% 99.0% 99.3%
225 99.3% 99.2% 99.3%
240 99.5% 99.3% 99.5%
255 99.7% 99.5% 99.7%
270 99.7% 99.5% 99.7%
285 99.7% 99.5% 99.7%
300 99.7% 99.5% 99.7%
315 99.7% 99.5% 99.7%
330 99.7% 99.5% 99.7%
345 99.7% 99.5% 99.7%
360 99.7% 99.5% 99.7%
420 100.0% 100.0% 100.0%
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Calculation of Trip Generation Time Distribution To compute the trip generation times, new time distributions (A, B, C, and D) are formed by applying a summing algorithm repeatedly to calculate the time distribution of an event that is dependent on two or more sequential activities. Table 4.7 shows the summing procedure and a description of each of the final trip generation distributions.
Table 4.7 Trip Generation Distributions Description Activities Distribution Description Sequence Time distribution of commuters evacuate directly, A employees live outside the EPZ, and transients 1+2 evacuate directly.
Time distribution of commuters/transients arriving B 1+2+3 home/residence.
Time distribution of residents wait for commuters and C transients arriving residence to begin the evacuation 1+2+3+4 trip.
Time distribution of residents without/do not wait for D commuters and transients at residence to begin the 1+4 evacuation trip.
The trip generation distributions describe the activities that take place before the evacuation trips begin. Distribution B is embedded within Distribution C because those residents are awaiting the return of the commuter and transients arriving at their residence before beginning their evacuation.
Statistical Outliers Some of the numeric responses are inconsistent with the overall pattern of results because the response either may be unrealistic or reflects a special population that need to be classified in a different population subgroup. These outliers may be valid responses that must be considered or unrepresentative and has to be dropped from the sample. To eliminate outliers:
a) Mean and standard deviation of the specific activity are estimated from the responses.
b) Median of the same data is estimated, with its position relative to the mean noted.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate c) The histogram of the data is inspected and all values greater than 3.5 standard deviations from the mean are flagged and either considered as a valid response or dropped from the sample.
d) All values greater than 4 standard deviations from the mean are considered outliers and dropped from the sample.
e) Repeat steps "a" to "d".
Mobilization Time Distributions The overall (or total) mobilization distributions are constructed using the different mobilization activities modeled. This is done by using the data sets and distributions under different scenarios (e.g. households with/without commuters, households that wait/dont wait for commuters, commuters/transients evacuate directly, commuters/transients returning to home/residence prior to evacuating) according to the flow chart presented in Figure 4.1. The mobilization times obtained under different scenarios are used as direct inputs to the simulation model that lead to the ETE. Table 4.8 shows the trip generation distributions A, C, and D on the same time scale (elapsed time) and Figure 4.2 presents a comparison for the trip generation time distributions for the daytime scenarios.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.8 Trip Generation Distributions (Daytime)
Trip Generation Distributions (Daytime)
Elapsed Distribution A Distribution C Distribution D Time (Minutes) Population Cumulative Population Cumulative Population Cumulative 0 0.0% 0.0% 0.00% 0.00% 0.00% 0.00%
15 5.8% 5.8% 0.00% 0.00% 0.00% 0.00%
30 35.5% 41.3% 0.00% 0.00% 11.21% 11.21%
45 45.4% 86.7% 2.11% 2.11% 29.99% 41.20%
60 12.4% 99.1% 10.53% 12.64% 22.73% 63.92%
75 0.9% 100.0% 19.09% 31.73% 18.04% 81.96%
90 21.65% 53.38% 9.11% 91.07%
105 18.10% 71.47% 4.12% 95.19%
120 12.28% 83.76% 0.89% 96.08%
150 10.44% 94.20% 2.25% 98.33%
180 3.45% 97.65% 1.67% 100.00%
240 2.30% 99.94%
300 0.06% 100.00%
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 4.2 Trip Generation Distributions Comparison (Daytime) 100%
Population Evacuating (%)
80%
60%
40%
Distribution A 20% Distribution C Distribution D 0%
0 50 100 150 200 250 300 Elapsed Time (min)
Using the same methodology, the trip generation time distributions A, C, and D for the nighttime and weekend scenarios were developed and are shown in Tables 4.9 and 4.10, respectively.
Figures 4.3 and 4.4 present the comparison for the trip generation distributions.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.9 Trip Generation Distributions (Nighttime)
Trip Generation Distributions (Nighttime)
Elapsed Distribution A Distribution C Distribution D Time Population Cumulative Population Cumulative Population Cumulative 0 0.0% 0.0% 0.00% 0.00% 0.00% 0.00%
15 5.8% 5.8% 0.00% 0.00% 0.00% 0.00%
30 35.5% 41.3% 0.00% 0.00% 10.56% 10.56%
45 45.4% 86.7% 1.98% 1.98% 28.85% 39.41%
60 12.4% 99.1% 10.04% 12.02% 23.40% 62.81%
75 0.9% 100.0% 18.62% 30.64% 18.80% 81.61%
90 21.70% 52.34% 8.90% 90.51%
105 18.40% 70.73% 3.96% 94.46%
120 12.40% 83.14% 1.19% 95.65%
150 10.59% 93.73% 2.67% 98.33%
180 3.83% 97.55% 1.67% 100.00%
240 2.39% 99.94%
300 0.06% 100.00%
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure 4.3 Trip Generation Distributions Comparison (Nighttime) 64 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.10 Trip Generation Distributions (Weekend)
Trip Generation Distributions (Weekend)
Elapsed Distribution A Distribution C Distribution D Time Population Cumulative Population Cumulative Population Cumulative 0 0.0% 0.0% 0.00% 0.00% 0.00% 0.00%
15 5.8% 5.8% 0.00% 0.00% 0.00% 0.00%
30 35.5% 41.3% 0.00% 0.00% 10.84% 10.84%
45 45.4% 86.7% 2.04% 2.04% 29.32% 40.15%
60 12.4% 99.1% 10.24% 12.28% 22.95% 63.11%
75 0.9% 100.0% 18.78% 31.06% 18.19% 81.29%
90 21.55% 52.61% 9.01% 90.30%
105 18.12% 70.73% 4.08% 94.38%
120 12.28% 83.01% 1.02% 95.40%
150 10.52% 93.53% 2.65% 98.05%
180 3.78% 97.30% 1.93% 99.98%
240 2.62% 99.93% 0.02% 100.00%
300 0.07% 100.00%
Figure 4.4 Trip Generation Distributions Comparison (Weekend) 65 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 4.1.1. Permanent Residents and Transient Population Permanent residents are household residents, residents in special facilities, residents in medical facilities, employees at work, and children at schools within the EPZ. Census data were used to generate residential population and the population is distributed to zones of the network based on spatial locations. Major employers in the area were also geocoded and spatially associated with zones. The total number of employees is dependent on time of day and time of week. It is assumed that each employee commutes to work separately.
The transient population refers to people staying in a hotel, motel or a campground. According to different scenarios, the total transient population and locations which they are at varies by weather, time of day and time of year. The total number of transient population is divided into three groups: 1) Transients in their residence when the order to evacuate is received and will evacuate directly from hotel/model/campground; 2) Transients away from their residence when the order to evacuate is issued, but will return to their residence prior to evacuating; 3)
Transients away from their residence when the order to evacuate is issued that will evacuate directly from where they are. The first two groups are assigned to the corresponding zones where the hotel/motel/campground are located. The third group of transient population is distributed evenly within the EPZ.
Assumptions regarding transients are scenario-specific and are detailed in each scenario described in Section 1.3.
4.1.2. Transit Dependent Permanent Residents Transit-dependent permanent residents are those residents within the EPZ who do not have access to a vehicle or are dependent on help from outside the home to evacuate. The estimated number of transit-dependent permanent residents was adapted from the results of the random telephone survey of the households in the EPZ and surrounding area and are described in detail in Section 2.2 and Table 2.6. It is estimated that buses would be available to pick up transit dependent residents approximately 120 minutes (obtain drivers, brief drivers and mobilize to bus routes) after the order to evacuate and that would allow individuals to make their way to a bus route.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate A subset of transit dependent residents includes people with disabilities and those with access and functional needs that live independent of a special facility. Information was requested from Roane County regarding residents who need assistance during an evacuation, but none was provided.
Because local emergency management agencies were not able to provide information regarding special needs individuals requiring assistance during an evacuation in the EPZ, the total number of vehicles needed was estimated as described in Section 2.2 and evenly distributed across the EPZ.
It is assumed that ambulances required to evacuate special needs individuals are capable of mobilizing to the home, loading the patient and begin the evacuation within 30 minutes of the evacuation order.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.11 Evacuation of Transit Dependent Individuals Summer Winter Summer Midweek Midweek Midweek Weekend Midweek Weekend Midweek Midweek Weekend Weekend Scenario 1 2 3 4 5 6 7 8 9 10*
Daytime Daytime Evening Daytime Daytime Evening Daytime Normal Adverse Normal Normal Normal Adverse Normal Normal Normal Weather Weather Weather Weather Weather Weather Weather Weather Weather Full EPZ 2:11 2:11 2:10 2:11 2:11 2:12 2:11 2:11 2:11 2:36 Times presented in Hours:Minutes
- Peak Construction Scenario 68 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 4.1.3. Special Facilities The presence of special facilities was researched during development of the ETE and it was determined that one facility, the Kingston Academy, currently exists within the EPZ. The Kingston Academy is a Psychiatric Residential Treatment Facility with living quarters and a capacity of 52 children between the ages of 5 and 17. The facility provides residential treatment and day treatment services. For this ETE, it is assumed the facility is at 90% capacity when an evacuation is ordered and the facility is ready to evacuate 75 minutes (60 minutes to prepare +
15 minutes to load vehicles) after the order to evacuate is issued. This results in an evacuation of approximately 47 residents from this facility. The number of transit-dependent residents in special facilities is summarized in Table 2.6.
Information on evacuation of the Kingston Academy is provided in Table 4.12.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.12 ETEs for Special Facility Populations Travel Mobilization Distance Outbound Loading Time to Number/Types Time to EPZ Travel ETE Facility Population Time EPZ of Vehicles Boundary Speed (hr:min)
(minutes) (minutes) Boundary (miles) (mph)
(minutes)
Kingston 47 3 Vans 75 15 2.58 45.32 3.416 1:19 Academy 70 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 4.2. Evacuation Time Estimate Modeling This Section of the report includes a discussion of INTEGRATION, the traffic simulation model used in performance of the ETE and a summary of the key inputs, assumptions, outputs, and computational process associated with the simulation. INTEGRATION is a microscopic traffic assignment and simulation program with broad applicability to traffic simulation activities well-suited for performance of ETEs for nuclear power plants. The INTEGRATION software calculates a number of Measures of Effectiveness (MOEs) which are addressed by NUREG/CR-7002. The INTEGRATION software is listed in the U.S. Department of Transportations (DOT) Evacuation Management Operations (EMO) Modeling Assessment:
Transportation Modeling Inventory, developed to support selection of an appropriate model for use in evacuation analyses (Reference 1).
INTEGRATION is an integrated simulation and traffic assignment model that performs traffic simulations by tracking the movement of individual vehicles every 1/10 of a second. This allows detailed analyses of lane-changing movements and shock wave propagations. It also permits considerable flexibility in representing spatial and temporal variations in traffic conditions. The model also estimates the expected number of vehicle crashes using a time-based crash prediction model.
The INTEGRATION model computes a number of MOEs, including the network efficiency.
Efficiency evaluation of highway alternatives involves computing the average speed and vehicle delay. The average vehicle speed is computed as the average of all vehicle speeds, where the vehicle speed is computed as the trip distance divided by the trip duration. This model has been validated against state-of-the-art delay estimation procedures using queuing theory and shockwave analysis and against standard traffic flow theory and has been utilized for the evaluation of real-life applications.
The calibration of the INTEGRATION software entails two calibration efforts, namely calibration of the traffic demand and calibration of the network supply. The calibration of the traffic demand involves the use of the telephone survey results to construct a time-varying origin-destination (O-D) table. Different O-D demands were constructed for the different scenarios that were identified in Section 1.3. The second calibration effort entails calibrating four roadway parameters: saturation flow rate; free-flow speed; speed-at-capacity; and jam density.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 4.2.1. Traffic Simulation Model Input Input files of INTEGRATION include files defining the topological relationship of the network, traffic control information and traffic demand data. The input files of the simulation include:
- Node File
- Link File
- Demand File
- Signal File
- Incident File
- Other supplemental Files The final network generated includes 1,824 nodes, 252 zones, and 3,312 links. Lane striping file is also included to define turning movements assigned to each lane at intersections.
4.2.2. Traffic Simulation Model Output INTEGRATION is flexible regarding simulation outputs and is capable of providing output files by network link, by vehicle, and by time sequences. At an aggregated level, INTEGRATION is capable of providing output results as: average vehicle stops/delays; total vehicles existing in the network; travel time/distance by vehicle class; volume/capacity ratio; and others. At individual link or vehicle level, INTEGRATION is capable of providing output results as:
Starting/ending time by vehicle and/or by link; link flow; link average travel speed; and queues on link, etc. Because the goal of the ETE is to estimate the time needed for the public to move out of the area of concern, the output file needed includes time and location information for each evacuating vehicle. By setting each evacuation vehicle as a probe vehicle, the appropriate output file records the trajectories of each vehicle. Data recorded in the output file are link and vehicle based. Once a vehicle exits a link, a record is written to the output file documenting time, trip ID, O-D, link ID, and vehicle speed. The data in the output file is then aggregated to calculate the travel time for each evacuating vehicle exiting the EPZ boundary by identifying the link ID at the boundary of the EPZ.
4.3. Evacuation Time Estimates for the General Public The output file provides a vehicle probe listing which chronicles the completion of each link a vehicle probe traverses. Every evacuating vehicle is marked as a probe in the simulation for 72 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate ETE. Two types of records can be produced, namely record type 11 and 21. Record type 11 is produced only once for each link and is generated at the time the vehicle departs the link.
Record type 21, in contrast, is produced every second the vehicle is on the link.
To compute the evacuation time, the following steps are adopted:
- 1. The phone survey asked questions such as whether or not the respondents will be at work, if yes, will they return home before evacuating, and how long will they need to prepare to evacuate. Such data are aggregated to develop trip generation times as described in Section 4.1. Several time distributions are generated to describe the time people need to prepare to evacuate. Such distributions are statistically aggregated to obtain the overall patterns of the time needed to prepare to evacuate.
- 2. The simulation starts with a 45 minute background traffic simulation to ensure equilibration prior to initiating the ETE simulation.
- 3. Following this 45 minute period, the background traffic gradually decreases and traffic volumes start to convert into evacuation traffic as INTEGRATION begins to generate and load vehicles into the network based on the trip generation time distribution.
- 4. At 90 minutes the background traffic will stop entering the network.
- 5. The simulation continues to simulate each vehicles movement and traffic condition in the network.
- 6. The output file records the trajectory of each vehicle and information such as origin, destination, starting time, and arrival time, etc.
- 7. The road links at the boundary of the EPZs are used to identify occurrence of each vehicle on the links. The travel time on such links are divided into 2 parts proportional on the length of the section of that link located within and out of the boundary.
- 8. The time spent traveling is documented and aggregated. The ETE is estimated for 90%
and 100% of the vehicle exiting the EPZs.
The ETE for the evacuation of the general public are provided in Tables 4.13 and 4.14.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table 4.13 ETEs for Evacuation of the General Public (90% of the Affected Population)
Summer Winter Summer Midweek Midweek Midweek Weekend Midweek Weekend Midweek Midweek Weekend Weekend Scenario 1 2 3 4 5 6 7 8 9 10*
Daytime Daytime Evening Daytime Daytime Evening Daytime Normal Adverse Normal Normal Normal Adverse Normal Normal Normal Weather Weather Weather Weather Weather Weather Weather Weather Weather Full EPZ 2:09 2:09 1:45 1:40 2:16 2:17 1:44 1:40 2:09 3:38 Times presented in Hours:Minutes
- Peak Construction Scenario Table 4.14 ETEs for Evacuation of the General Public (100% of the Affected Population)
Summer Winter Summer Midweek Midweek Midweek Weekend Midweek Weekend Midweek Midweek Weekend Weekend Scenario 1 2 3 4 5 6 7 8 9 10*
Daytime Daytime Evening Daytime Daytime Evening Daytime Normal Adverse Normal Normal Normal Adverse Normal Normal Normal Weather Weather Weather Weather Weather Weather Weather Weather Weather Full EPZ 3:43 3:43 3:05 3:03 3:52 3:52 3:10 3:01 3:43 4:07 Times presented in Hours:Minutes
- Peak Construction Scenario 74 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 5.0 OTHER CONSIDERATIONS The preceding sections describe the methodology and approach to calculating the ETE. In addition to the calculation of an ETE, there are other considerations that need to be addressed in this and future ETE studies. These considerations, as appropriate, are described below.
5.1. Development of Traffic Control Plans In the event of an evacuation of the EPZ, OROs would establish ACPs and Traffic Control Points (TCPs) as necessary to support the evacuation. It is assumed that ACPs can be staffed within approximately 90 minutes of the advisory to evacuate. Activation of ACPs prior to 90 minutes could delay commuters returning from areas outside of the EPZ. Therefore, it is recommended that ACPs be established 90 minutes following an advisory to evacuate to allow commuters sufficient time to return home and prepare for an evacuation.
ACPs should be established as follows to restrict in-bound traffic flow toward the CRN Site:
- 1. Prior to 45 minutes after the evacuation order is issued, background and pass-through traffic is running normally in the network.
- 2. From the time an evacuation order is issued until 90 minutes after the order is issued, background traffic begins to diminish as traffic exits the EPZ and the ACPs begin to prevent inbound traffic from entering the EPZ. The evacuating traffic begins to increase at the rate of the time distribution to get ready (see section 4.1).
- 3. The background and pass-through traffic stops entering the EPZ 90 minutes after the evacuation order is issued.
Based on the low population of the EPZ, the limited number of vehicles involved in the evacuation, the relative simplicity of the roadway network within the EPZ, and the absence of congestion observed during the traffic simulation modeling, the need to develop more detailed traffic control plans to support an evacuation is not considered necessary at this time. As future ETE studies are conducted additional consideration should be given to the need for a more detailed traffic control plan based on future potential changes to the roadway network, the potential for increased populations within the EPZ and the potential for increased congestion observed during traffic simulation modeling.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 5.2. Enhancements in Evacuation Time Guidance presented in NUREG/CR-7002 suggests that an evaluation of potential enhancements that could reduce the evacuation time be limited to those roadways or intersections of the EPZ that impact the ETE the greatest (Reference 4). These evaluations typically include intersections and roadways that experience LOS F conditions for some period of time. Based on the absence of congestion observed during the traffic simulation modeling, the need to develop enhancements that may reduce evacuation times would have little, if any, benefit. As future ETE studies are conducted, additional consideration should be given to the need for enhancements that may reduce evacuation times.
5.3. State and Local Review State and local authorities were involved in the development of the ETE. Interactions began with a kick-off meeting in Knoxville in January 2014 during which the regulatory requirements, the process used to develop the ETE and the associated data and information needs were discussed. The meeting was attended by representatives of the following State and local agencies and private sector support organizations:
- Tennessee Highway Patrol
- Roane County Office of Emergency Services and Homeland Security
- Anderson County Office of Emergency Management and Homeland Security
- Loudon County Mayor
- Loudon County Homeland Security and Emergency Management Agency
- Loudon County Sheriffs Office
- Knox County Emergency Management Agency
- Knox County Sheriffs Office
- Knox County Engineering 76 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate
- City of Oak Ridge Fire Department
- Kingston Police Department
- Lenoir City Fire Department
- Rural/Metro of East Tennessee
- American Red Cross of East Tennessee Following the kick-off meeting, a telephone survey instrument was prepared and provided to the TEMA for review and comment, resulting in several modifications. Each agency approved of the instrument prior to initiating the telephone survey.
TEMA and Roane County provided assistance with completing data collection related to the permanent resident and transient populations, schools, major employers, transportation resources, transit-dependent residents and hotels, motels and campgrounds in the EPZ.
5.4. Reviews and Updates Details related to updating this ETE are included in Sections 5.6 and 5.7 of this report.
5.5. Reception Centers and Congregate Care Centers The specific locations of reception centers have not yet been identified. Because of the absence of a school population and the limited number of transit-dependent permanent residents, it is not anticipated that multiple trips will be necessary to evacuate the transit dependent population. Therefore the location of these facilities and the logistics of offloading passengers will not impact return trips to the EPZ or the evacuation time.
5.6. New Reactors Part 5 of the Early Site Permit Application (ESPA) being submitted for the CRN Site includes two (2) Emergency Plans (Part 5A and Part 5B) for review by the NRC. Part 5A will address a site boundary Emergency Planning Zone (EPZ) and Part 5B addresses a 2-Mile EPZ. The final EPZ size will be determined at the time the Combined License Application (COLA) is submitted.
This ETE is prepared in support of the 2-Mile EPZ Emergency Plan. In the event the site boundary EPZ is selected for the CRN Site, the Tennessee Valley Authority (TVA) has 77 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate proposed an exemption from the requirements to perform an ETE and an update to this ETE will not be necessary.
Because the CRN Site is a greenfield site, as described in NUREG/CR-7002, emergency response plans are not in place, evacuation plans have not been approved and tested by local authorities and the locations of congregate care and reception centers have not been established. These conditions necessitate that the development of the ETE analysis be coordinated with the development of the emergency response program being prepared during the licensing phase (Reference 4). For the CRN Site, development of the offsite emergency response program will occur beginning with the development of the COLA. In the event a 2-mile EPZ is selected, assumptions used in the ETE must be consistent with the assumptions and proposed resources and infrastructure identified within the emergency response plan to provide an accurate ETE. An ETE update for the COLA is expected to be developed based on the most recent decennial census data projected to the year the license application will be submitted.
5.7. Early Site Permits This ETE was developed in support of the CRN Site ESPA. The ETE serves to satisfy the requirements of 10 CFR 52.17(b)(1), which states that the site safety analysis report identify physical characteristics of the proposed site, such as egress limitations from the area surrounding the site, that could pose a significant impediment to the development of emergency plans and if physical impediments are identified, the application must identify measures that would, when implemented, mitigate or eliminate the significant impediment. This ETE did not identify physical characteristics of the proposed site that could pose a significant impediment to the development of emergency plans.
As described in Section 5.6 and in Section 5.7 of NUREG/CR-7002, data and information is expected to be updated, as appropriate, to ensure up-to-date information is used to develop the ETE when the COLA is submitted.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate 6.0 GLOSSARY Count Station - Specific location on a roadway where traffic count surveys are conducted.
Demand Estimation - The total number of evacuees by population group including vehicles.
Emergency Response Planning Areas (ERPAs) - Defined areas that constitute the EPZ and for which emergency response plans have been developed. These areas are typically defined by geographic or political boundaries to support emergency response planning and may also be referred to as subareas, protective action areas, or other local terminology.
Evacuation Tail - A small portion of the population that takes a longer time to evacuate than the rest of the general public and is the last to leave the evacuation area. The tail generally conforms to about the last 10 percent of the population.
Keyhole Evacuation - An evacuation of the 2-mile radius around an NPP and the downwind sectors forming a keyhole configuration.
Link - A segment of roadway between two nodes.
Loading Curve - The rate at which vehicles are entered onto the roadway network.
Measure of Effectiveness (MOE) - Statistics used to describe performance. As applied in this document, these include output data that provide key performance characteristics of the roadway network and the evacuation time.
Node - An identification designator used to connect links in a roadway network model or to apply input data onto the network. Nodes are at intersections, ramps, etc., and contain characteristics such as traffic control and may be used as input points to assign loading of vehicles.
Permanent Resident - All people having a residence in the area.
Roadway Capacity - The maximum rate at which vehicles can be reasonably expected to traverse a point or uniform section of roadway during a given time period under prevailing conditions.
Shadow Evacuation - Evacuation of persons from areas outside any officially declared evacuation zone.
Special Event - An activity where large transient populations are present for a limited period of time.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Special Facilities - Facilities where residents are confined or dependent upon facility personnel for transportation, including nursing homes, assisted living centers, hospitals, jails, prisons, and other similar facilities.
Staged Evacuation - A protective action where one area is ordered to evacuate while adjacent areas are ordered to shelter in place until ordered to evacuate.
Transient Population - Tourists, shoppers, employees, etc., who do not reside within the EPZ, and other people temporarily visiting the EPZ.
Trip Generation Time - Time elapsed for each population group from when the evacuation order was disseminated until the time when the evacuation trip actually begins (e.g., when the car leaves the driveway).
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate
7.0 REFERENCES
- 1. U.S. Department of Transportations (DOT) Evacuation Management Operations (EMO)
Modeling Assessment: Transportation Modeling Inventory, June 2008
- 2. Nuclear Regulatory Commission (NRC). NUREG/CR-6953, Vol. II, SAND2007-4195P, Review of NUREG-0654, Supplement 3, Criteria for Protective Action Recommendations for Severe Accidents - Focus Groups and Telephone Survey, October 2008.
- 3. Institute for Environmental Studies (IES), University of Toronto. The Mississauga Evacuation Final Report, June 1981.
- 4. Nuclear Regulatory Commission (NRC). NUREG/CR-7002, Vol. II, SAND2010-0016P, Criteria for Development of Evacuation Time Estimates, November 2011.
- 5. Nuclear Regulatory Commission (NRC). NUREG-0654/FEMA-REP-1, Rev. 1. Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, November 1980.
- 6. Transportation Research Board (TRB). Highway Capacity Manual. National Research Council, Washington, DC, 2010.
- 7. American Association of State Highway and Transportation Officials (AASHTO). A Policy on Geometric Design of Highways and Streets. AASHTO, Washington, DC, 2011.
- 8. Federal Highway Administration (FHWA). Identifying and Assessing Key Weather- Related Parameters and Their Impacts on Traffic Operations Using Simulation. U.S. Department of Transportation. Publication No. FHWA-HRT-04-131. September 2004.
- 9. Federal Emergency Management Agency (FEMA). Radiological Emergency Preparedness Program Manual. FEMA-P-1028. January 2015.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Appendices Appendix A Roadway Network Characteristics Appendix B Evacuation Time Estimate Evaluation Criteria Checklist Appendix C Traffic Simulation Model Inputs and Outputs 82 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Appendix A - Roadway Network Characteristics 83 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table A.1 Node Input File Node Node Node ID X-Coordinate Y-Coordinate Category Attribute 51 221.805 241.105 1 -51 59 248.935 203.993 1 -59 111 209.333 236.852 1 -111 185 224.818 260.019 1 -185 186 224.391 256.883 1 -186 188 231.454 249.464 1 -188 226 232.948 221.259 1 -226 301 244.246 209.738 4 0 302 243.991 209.856 4 0 369 247.79 211.173 4 0 370 242.104 207.672 4 0 371 246.2 209.016 4 0 376 242.807 207.75 4 0 560 248.192 211.435 4 0 578 242.109 207.328 4 0 579 248.349 211.205 4 0 882 232.1 207.485 4 0 883 232.605 208.059 4 0 890 273.447 220.325 4 0 891 271.605 220.361 4 0 893 261.13 218.709 4 0 895 273.497 220.582 4 0 896 271.483 220.625 4 0 897 261.233 218.477 4 0 898 263.51 219.481 4 0 899 263.712 219.274 4 0 1051 225.561 255.992 4 0 1052 224.793 256.579 4 0 1054 221.324 241.242 4 0 84 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Node Node Node ID X-Coordinate Y-Coordinate Category Attribute 1055 221.076 241.515 4 0 1133 211.705 233.162 4 0 1167 203.114 224.989 4 0 1168 219.167 239.52 4 0 1306 230.115 205.111 4 0 1307 235.216 210.188 4 0 1323 224.818 251.153 4 0 1324 225.079 252.877 4 0 1386 204.759 226.558 4 0 1387 207.392 229.064 4 0 1480 240.31 212.359 4 0 1481 235.771 210.486 4 0 1505 222.462 242.359 4 0 1506 222.913 242.888 4 0 1523 208.361 229.979 4 0 1524 208.655 230.261 4 0 1579 226.595 261.191 4 0 1580 225.887 258.139 4 0 1581 225.748 257.227 4 0 1582 225.826 255.774 4 0 1583 225.21 253.711 4 0 85 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table A.2 Link Input File Speed First First Second Number Density Second Link ID From To Length Limit Capacity Signal Phase Releasing Releasing of Lanes (V/KM/Lane) Phase (mph) Releasing Direction Direction 17 301 302 0.028 45 1900 1 150 0 0 0 0 0 74 369 301 0.382 55 1900 1 150 -67 2 111 0 0 75 301 370 0.298 45 1900 1 150 0 0 0 0 0 76 371 301 0.212 45 1900 1 150 -67 1 111 0 0 80 376 371 0.363 55 1900 1 150 -68 2 111 0 0 239 560 369 0.048 80 2000 2 150 0 0 0 0 0 257 369 370 0.668 80 2000 2 150 0 0 0 0 0 258 578 376 0.082 80 2000 2 150 0 0 0 0 0 259 376 579 0.653 80 2000 2 150 0 0 0 0 0 495 882 883 0.077 45 1900 1 150 0 0 0 0 0 503 891 890 0.184 80 2000 2 150 0 0 0 0 0 504 890 892 1.046 80 2000 2 150 0 0 0 0 0 505 893 560 1.487 80 2000 2 150 0 0 0 0 0 506 894 895 1.047 80 2000 2 150 0 0 0 0 0 507 895 896 0.202 80 2000 2 150 0 0 0 0 0 508 579 897 1.482 80 2000 2 150 0 0 0 0 0 509 898 893 0.25 80 2000 2 150 0 0 0 0 0 510 897 899 0.26 80 2000 2 150 0 0 0 0 0 637 1051 1052 0.097 30 1900 1 150 0 0 0 0 0 639 51 1054 0.051 30 1900 1 150 10001 0 0 0 0 86 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Speed First First Second Number Density Second Link ID From To Length Limit Capacity Signal Phase Releasing Releasing of Lanes (V/KM/Lane) Phase (mph) Releasing Direction Direction 640 1054 1055 0.037 30 1900 1 150 0 0 0 0 0 650 59 371 0.58 30 1900 1 150 -68 1 111 0 0 733 896 898 0.808 80 2000 2 150 0 0 0 0 0 734 899 891 0.799 80 2000 2 150 0 0 0 0 0 755 1133 111 0.45 30 1900 1 150 0 0 0 0 0 757 1055 113 1.566 30 1900 1 150 0 0 0 0 0 798 913 1167 0.803 55 1900 1 150 0 0 0 0 0 799 1133 1168 0.981 55 1900 1 150 0 0 0 0 0 874 371 579 0.313 45 1900 1 150 0 0 0 0 0 993 1305 1306 1.469 45 1900 1 150 0 0 0 0 0 994 1306 882 0.319 45 1900 1 150 0 0 0 0 0 995 883 1307 0.338 45 1900 1 150 0 0 0 0 0 1010 1323 1324 0.174 55 1900 1 150 0 0 0 0 0 1097 1167 1386 0.227 55 1900 1 150 0 0 0 0 0 1098 1386 1387 0.363 55 1900 1 150 0 0 0 0 0 1263 302 1480 0.49 45 1900 1 150 0 0 0 0 0 1264 1481 1480 0.495 45 1900 1 150 0 0 0 0 0 1265 1307 1481 0.063 45 1900 1 150 0 0 0 0 0 1303 1505 1506 0.07 55 1900 1 150 0 0 0 0 0 1328 1168 1054 0.276 55 1900 1 150 0 0 0 0 0 1329 1054 1505 0.16 55 1900 1 150 0 0 0 0 0 87 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Speed First First Second Number Density Second Link ID From To Length Limit Capacity Signal Phase Releasing Releasing of Lanes (V/KM/Lane) Phase (mph) Releasing Direction Direction 1330 1506 1323 0.855 55 1900 1 150 0 0 0 0 0 1331 1387 1523 0.133 55 1900 1 150 0 0 0 0 0 1332 1523 1524 0.041 55 1900 1 150 0 0 0 0 0 1333 1524 1133 0.421 55 1900 1 150 0 0 0 0 0 1419 185 1579 0.223 30 1900 1 150 10001 0 0 0 0 1420 1052 186 0.05 30 1900 1 150 0 0 0 0 0 1421 1580 1579 0.315 55 1900 1 150 0 0 0 0 0 1422 1579 914 0.429 55 1900 1 150 0 0 0 0 0 1423 1581 1580 0.092 55 1900 1 150 0 0 0 0 0 1424 1051 1581 0.125 55 1900 1 150 0 0 0 0 0 1425 1582 1051 0.034 30 1900 1 150 10001 0 0 0 0 1426 1324 1583 0.084 55 1900 1 150 0 0 0 0 0 1427 1583 1051 0.231 55 1900 1 150 0 0 0 0 0 1435 188 1582 0.856 30 1900 1 150 0 0 0 0 0 1810 1420 578 2.983 80 2000 2 150 0 0 0 0 0 1811 370 1801 2.983 80 2000 2 150 0 0 0 0 0 1875 1481 226 1.273 30 1900 1 150 0 0 0 0 0 1925 302 301 0.028 45 1900 1 150 -67 1 111 0 0 1945 301 371 0.212 45 1900 1 150 -68 1 111 0 0 2224 883 882 0.077 45 1900 1 150 0 0 0 0 0 2348 1052 1051 0.097 30 1900 1 150 10001 0 0 0 0 88 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Speed First First Second Number Density Second Link ID From To Length Limit Capacity Signal Phase Releasing Releasing of Lanes (V/KM/Lane) Phase (mph) Releasing Direction Direction 2350 1054 51 0.051 30 1900 1 150 0 0 0 0 0 2351 1055 1054 0.037 30 1900 1 150 10001 0 0 0 0 2361 371 59 0.58 30 1900 1 150 0 0 0 0 0 2454 111 1133 0.45 30 1900 1 150 10001 0 0 0 0 2456 113 1055 1.566 30 1900 1 150 0 0 0 0 0 2495 1167 913 0.803 55 1900 1 150 0 0 0 0 0 2496 1168 1133 0.981 55 1900 1 150 0 0 0 0 0 2567 579 371 0.313 45 1900 1 150 0 0 0 0 0 2682 1306 1305 1.469 45 1900 1 150 0 0 0 0 0 2683 882 1306 0.319 45 1900 1 150 0 0 0 0 0 2684 1307 883 0.338 45 1900 1 150 0 0 0 0 0 2696 1324 1323 0.174 55 1900 1 150 0 0 0 0 0 2762 1386 1167 0.227 55 1900 1 150 0 0 0 0 0 2763 1387 1386 0.363 55 1900 1 150 0 0 0 0 0 2903 1480 302 0.49 45 1900 1 150 0 0 0 0 0 2904 1480 1481 0.495 45 1900 1 150 0 0 0 0 0 2905 1481 1307 0.063 45 1900 1 150 0 0 0 0 0 2942 1506 1505 0.07 55 1900 1 150 0 0 0 0 0 2967 1054 1168 0.276 55 1900 1 150 0 0 0 0 0 2968 1505 1054 0.16 55 1900 1 150 0 0 0 0 0 2969 1323 1506 0.855 55 1900 1 150 0 0 0 0 0 89 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Speed First First Second Number Density Second Link ID From To Length Limit Capacity Signal Phase Releasing Releasing of Lanes (V/KM/Lane) Phase (mph) Releasing Direction Direction 2970 1523 1387 0.133 55 1900 1 150 0 0 0 0 0 2971 1524 1523 0.041 55 1900 1 150 0 0 0 0 0 2972 1133 1524 0.421 55 1900 1 150 0 0 0 0 0 3052 1579 185 0.223 30 1900 1 150 0 0 0 0 0 3053 186 1052 0.05 30 1900 1 150 0 0 0 0 0 3054 1579 1580 0.315 55 1900 1 150 0 0 0 0 0 3055 914 1579 0.429 55 1900 1 150 0 0 0 0 0 3056 1580 1581 0.092 55 1900 1 150 0 0 0 0 0 3057 1581 1051 0.125 55 1900 1 150 0 0 0 0 0 3058 1051 1582 0.034 30 1900 1 150 0 0 0 0 0 3059 1583 1324 0.084 55 1900 1 150 0 0 0 0 0 3060 1051 1583 0.231 55 1900 1 150 0 0 0 0 0 3068 1582 188 0.856 30 1900 1 150 0 0 0 0 0 3353 226 1481 1.273 30 1900 1 150 10001 0 0 0 0 90 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table A.3 Intersection Control Type Counts Intersection Control Type # of Intersections Traffic Light 2 Stop Signs 7 Yield Signs 0 Table A.4 Intersection Control Summaries Node ID X-Coordinate Y-Coordinate Control Type Notes 301 244.246 209.738 Traffic Light T-intersection 371 246.2 209.016 Traffic Light T-intersection 1051 225.561 255.992 Stop Sign 2-way 1054 221.324 241.242 Stop Sign 2-way 1133 211.705 233.162 Stop Sign 1-way 1481 235.771 210.486 Stop Sign 1-way 1579 226.595 261.191 Stop Sign 1-way 91 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table A.5 Summary of Signalized Intersections Initial Minimum Maximum Inter Inter Inter Green Green Green Optimization Cycle Cycle Cycle Signal Number Green Green Green Signal ID Time 1 Time 2 Time 3 Frequency Time Length Length Offset Phases Time 1 Time 2 Time 3 (sec) (sec) (sec) (sec)
(sec) (sec) (sec) (sec) (sec) (sec) 67 75 65 85 0 3 10 5 14 6 34.5 5.5 300 68 75 65 85 -3 3 10 5 14 6 34.5 5.5 300 Times listed in Seconds (sec).
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Appendix B - Evacuation Time Estimate Review Criteria Checklist 93 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table B.1 - Evacuation Time Estimate Review Criteria Checklist Criterion Addressed Comments in ETE Analysis (Yes/No) 1.0 Introduction
- a. The emergency planning zone (EPZ) and surrounding area should be Yes Section 1.0 described. Figure 1.1
- b. A map should be included that identifies primary features of the site, including Yes major roadways, significant topographical features, boundaries of counties, Figure 1.1 and population centers within the EPZ.
- c. A comparison of the current and previous ETE should be provided and Yes includes similar information as identified in Table 1-1, ETE Comparison, of Table 1.1 NUREG/CR-7002.
1.1 Approach
- a. A discussion of the approach and level of detail obtained during the field Yes survey of the roadway network should be provided.
- b. Sources of demographic data for schools, special facilities, large employers, Yes and special events should be identified.
Section 1.1
- c. Discussion should be presented on use of traffic control plans in the analysis. Yes
- d. Traffic simulation models used for the analyses should be identified by name Yes and version.
- e. Methods used to address data uncertainties should be described. Yes 1.2 Assumptions
- a. The planning basis for the ETE includes the assumption that the evacuation Yes Section 1.2 is ordered promptly and no early protective actions have been implemented.
- b. Assumptions consistent with Table 1-2, General Assumptions, of Yes Section 1.2 NUREG/CR-7002 should be provided and include the basis to support their use. Table 1.2 1.3 Scenario Development
- a. The ten scenarios in Table 1-3, Evacuation Scenarios, should be Yes Section 1.3 developed for the ETE analysis, or a reason should be provided for use of other scenarios. Table 1.3 94 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No) 1.3.1 Staged Evacuation
- a. A discussion should be provided on the approach used in development of a No Because this ETE analysis for the CRN Site staged evacuation. considers an EPZ encompassing an approximate 2 mile radius around the proposed reactor center point location, staged and traditional keyhole evacuations are not appropriate for the CRN Site and have not been considered in this analysis.
Instead this analysis considers an evacuation of the entire EPZ for each evacuation scenario.
Refer to Section 1.3.1 1.4 Evacuation Planning Areas
- a. A map of the EPZ with emergency response planning areas (ERPAs) should No The EPZ is an area encompassing an be included. approximate 2 mile radius around the proposed
- b. A table should be provided identifying the ERPAs considered for each ETE No reactor center point location. During an calculation by downwind direction in each sector. emergency at the CRN Site, protective actions will be implemented consistently throughout the EPZ.
- c. A table similar to Table 1-4, Evacuation Areas for a Staged Evacuation No For this reason, development of ERPA within the Keyhole, of NUREG/CR-7002 should be provided and includes the complete EPZ are not necessary to support site-specific evacuation of the 2, 5, and 10 mile areas and for the 2 mile area/5 mile protective action recommendation logic (i.e.,
keyhole evacuations. staged or keyhole based on wind direction) and ERPA are not considered in this analysis.
Refer to Section 1.4 Figure 1.1 2.0 Demand Estimation
- a. Demand estimation should be developed for the four population groups, Yes including permanent residents of the EPZ, transients, special facilities, and Section 2.0 schools.
2.1 Permanent Residents and Transient Population
- a. The US Census should be the source of the population values, or another Yes Section 2.1 95 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No) credible source should be provided.
- b. Population values should be adjusted as necessary for growth to reflect Yes population estimates to the year of the ETE.
- c. A sector diagram should be included, similar to Figure 2-1, Population by Yes Sector, of NUREG/CR-7002, showing the population distribution for Figure 2.1 permanent residents.
2.1.1 Permanent Residents with Vehicles
- a. The persons per vehicle value should be between 1 and 2 or justification Yes Section 2.1 should be provided for other values.
- b. Major employers should be listed. Yes Section 2.5 Table 2.7 2.1.2 Transient Population
- a. A list of facilities which attract transient populations should be included, Yes Section 2.1.1 and peak and average attendance for these facilities should be listed. The source of information used to develop attendance values should be provided. Table 2.5
- b. The average population during the season should be used, itemized and Yes Table 2.5 totaled for each scenario.
- c. The percent of permanent residents assumed to be at facilities should be Yes Section 2.1.2 estimated.
- d. The number of people per vehicle should be provided. Numbers may vary by Yes Section 2.1.2 scenario, and if so, discussion on why values vary should be provided.
- e. A sector diagram should be included, similar to Figure 2-1 of NUREG/CR- Yes Figure 2.2 7002, showing the population distribution for the transient population.
2.2 Transit Dependent Permanent Residents
- a. The methodology used to determine the number of transit dependent Yes Section 2.2 residents should be discussed
- b. Transportation resources needed to evacuate this group should be Yes Section 2.2 quantified.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No)
- c. The county/local evacuation plans for transit dependent residents should be No A county/local evacuation plan for transit-used in the analysis. dependent residents does not currently exist.
- d. The methodology used to determine the number of people with disabilities Yes Section 2.2 and those with access and functional needs who may need assistance and do not reside in special facilities should be provided. Data from local/county registration programs should be used in the estimate, but should not be the only set of data.
- e. Capacities should be provided for all types of transportation resources. Bus Yes Section 2.2 seating capacity of 50% should be used or justification should be provided for higher values.
- f. An estimate of this population should be provided and information should be Yes Section 2.2 provided that the existing registration programs were used in developing the estimate.
- g. A summary table of the total number of buses, ambulances, or other Yes Table 2.6 transport needed to support evacuation should be provided and the quantification of resources should be detailed enough to assure double counting has not occurred.
2.3 Special Facility Residents
- a. A list of special facilities, including the type of facility, location, and average Yes Section 2.3 population should be provided. Special facility staff should be included in the total special facility population. Table 2.6
- b. A discussion should be provided on how special facility data was obtained. Yes Section 2.3
- c. The number of wheelchair and bed-bound individuals should be provided. Yes Section 2.3
- d. An estimate of the number and capacity of vehicles needed to support the Yes Table 2.6 evacuation of the facility should be provided.
- e. The logistics for mobilizing specially trained staff (e.g., medical support or Yes Section 2.3 security support for prisons, jails, and other correctional facilities) should be discussed when appropriate.
2.4 Schools
- a. A list of schools including name, location, student population, and No Not Applicable transportation resources required to support the evacuation, should be 97 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No) provided. The source of this information should be provided.
- b. Transportation resources for elementary and middle schools are based on No The presence of schools was researched during 100% of the school capacity. development of the ETE and it was determined that no schools currently exist within the EPZ.
- c. The estimate of high school students who will use their personal vehicle to No evacuate should be provided and a basis for the values used should be provided Refer to Section 2.4
- d. The need for return trips should be identified if necessary. No 2.5.1 Special Events
- a. A complete list of special events should be provided and includes information Yes There were no special events identified that take on the population, estimated duration, and season of the event. place within the EPZ. However, it is assumed that
- b. The special event that encompasses the peak transient population should Yes the Smokin the Water 4th of July Celebration in be analyzed in the ETE. Kingston, Tennessee would result in a peak transient population within the EPZ. Based on the
- c. The percent of permanent residents attending the event should be Yes small permanent resident population in the EPZ, it estimated. is assumed that all permanent residents remain in the EPZ during this event and no reduction in permanent resident population is considered.
Refer to Section 2.5.1 2.5.2 Shadow Evacuation
- a. A shadow evacuation of 20 percent should be included for areas outside the Yes Section 2.5.2 evacuation area extending to 15 miles from the NPP.
- b. Population estimates for the shadow evacuation in the 10 to 15 mile area No Based on the reduced EPZ size, the population beyond the EPZ are provided by sector. estimates are available by sector from the EPZ boundary out to 15 miles was considered in the ETE.
Refer to Section 2.5.2
- c. The loading of the shadow evacuation onto the roadway network should be Yes.
consistent with the trip generation time generated for the permanent resident Section 2.5.2 population.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No) 2.5.3 Background and Pass Through Traffic
- a. The volume of background traffic and pass-through traffic should be based Yes Section 2.5.3 on the average daytime traffic. Values may be reduced for nighttime Table 2.9 scenarios.
- b. Pass-through traffic should be assumed to have stopped entering the EPZ No An estimate of 90 minutes is used in this analysis.
about two hours after the initial notification.
2.6 Summary of Demand Estimation
- a. A summary table should be provided that identifies the total populations and Yes Table 2.8 total vehicles used in the analysis for permanent residents, transients, transit Table 2.9 dependent residents, special facilities, schools, shadow population, and pass-through demand used in each scenario.
3.0 Roadway Capacity
- a. The method(s) used to assess roadway capacity should be discussed. Yes Section 3.0 3.1 Roadway Characteristics
- a. A field survey of key routes within the EPZ has been conducted. Yes Section 3.1
- b. Information should be provided describing the extent of the survey, and Yes Section 3.1 types of information gathered and used in the analysis.
- c. A table similar to that in Appendix A, Roadway Characteristics, of Yes Appendix A NUREG/CR-7002 should be provided.
- d. Calculations for a representative roadway segment should be provided. Yes Appendix A
- e. A legible map of the roadway system that identifies node numbers and Yes Figure 3.1 segments used to develop the ETE should be provided and should be similar to Figure 3-1, Roadway Network Identifying Nodes and Segments, of NUREG/CR-7002.
3.2 Capacity Analysis
- a. The approach used to calculate the roadway capacity for the transportation Yes Section 3.2 network should be described in detail and identifies factors that are expressly used in the modeling.
- b. The capacity analysis identifies where field information should be used in Yes Section 3.2 the ETE calculation.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No) 3.3 Intersection Control
- a. A list of intersections should be provided that includes the total numbers of Yes Section 3.3 intersections modeled that are unsignalized, signalized, or manned by response personnel.
- b. Characteristics for the 10 highest volume intersections within the EPZ are provided including the location, signal cycle length, and turn lane queue capacity.
- c. Discussion should be provided on how time signal cycle is used in the Yes Section 3.3 calculations.
3.4 Adverse Weather
- a. The adverse weather condition should be identified and the effect of Yes Section 3.4 adverse weather on mobilization should be considered.
- b. The speed and capacity reduction factors identified in Table 3-1, Weather Yes Table 3.3 Capacity Factors, of NUREG/CR-7002 should be used or a basis should be provided for other values.
- c. The study identifies assumptions for snow removal on streets and Yes Section 3.4 driveways, when applicable.
4.0 Development of Evacuation Times 4.1 Trip Generation Times
- a. The process used to develop trip generation times should be identified. Yes Section 4.1
- b. When telephone surveys are used, the scope of the survey, area of the Yes Section 1.1 survey, number of participants, and statistical relevance should be provided.
- c. Data obtained from telephone surveys should be summarized. Yes Table 1.2 Section 2.2 Table 4.4 Table 4.5 Table 4.6
- d. The trip generation time for each population group should be developed Yes Section 4.1 from site specific information.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No) 4.1.1 Permanent Resident and Transient Population
- a. Permanent residents are assumed to evacuate from their homes but are Yes Section 4.1 not assumed to be at home at all times. Trip generation time includes the assumption that a percentage of residents will need to return home prior to evacuating.
- b. Discussion should be provided on the time and method used to notify Yes Section 4.1 transients. The trip generation time discusses any difficulties notifying persons in hard to reach areas such as on lakes or in campgrounds.
- c. The trip generation time accounts for transients potentially returning to Yes Section 4.1 hotels prior to evacuating.
- d. Effect of public transportation resources used during special events where No Not applicable.
a large number of transients are expected should be considered.
Refer to Section 2.5.1.
- e. The trip generation time for the transient population should be integrated Yes Section 4.1 and loaded onto the transportation network with the general public.
4.1.2 Transit Dependent Residents
- a. If available, existing plans and bus routes are used in the ETE analysis. If No Not applicable.
new plans are developed with the ETE, they should have been agreed upon by the responsible authorities.
- b. Discussion should be included on the means of evacuating ambulatory Yes Section 4.1.2 and non-ambulatory residents. Section 2.2
- c. The number, location and availability of buses, and other resources Yes Section 4.1.2 needed to support the demand estimation are provided.
- d. Logistical details, such as the time to obtain buses, brief drivers and Yes Section 4.1.2 initiate the bus route are provided.
- e. Discussion should identify the time estimated for transit dependent Yes Section 4.1.2 residents to prepare and then travel to a bus pickup point, and describes the expected means of travel to the pickup point.
- f. The number of bus stops and time needed to load passengers should be No Refer to Section 4.1.2 discussed.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No)
- g. A map of bus routes should be included. Yes 4.1.2
- h. The trip generation time for non-ambulatory persons includes the time to Yes Section 4.1.2 mobilize ambulances or special vehicles, time to drive to the home of residents, loading time, and time to drive out of the EPZ should be provided.
- i. Information should be provided to support analysis of return trips, if No No return trips are necessary.
necessary.
4.1.3 Special Facilities
- a. Information on evacuation logistics and mobilization times should be Yes Section 2.3 provided.
Table 4.11
- b. Discussion should be provided on the inbound and outbound speeds. Yes Table 4.11
- c. The number of wheelchair and bed-bound individuals should be provided, Yes Section 2.3 and the logistics of evacuating these residents should be discussed.
- d. Time for loading of residents should be provided. Yes Table 4.11
- e. Information should be provided that indicates whether the evacuation can Yes Section 2.3 be completed in a single trip or if additional trips are needed.
- f. If return trips are needed, the destination of vehicles should be provided. No No return trips are necessary.
- g. Discussion should be provided on whether special facility residents are No Not applicable as no return trips are necessary.
expected to pass through the reception center prior to being evacuated to their final destination.
- h. Supporting information should be provided to quantify the time elements No Not applicable as no return trips are necessary.
for the return trips.
4.1.4 Schools
- a. Information on evacuation logistics and mobilization times should be No Not Applicable provided.
- b. Discussion should be provided on the inbound and outbound speeds. No The presence of schools was researched during
- c. Time for loading of students should be provided. No development of the ETE and it was determined
- d. Information should be provided that indicates whether the evacuation can No that no schools currently exist within the EPZ.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No) be completed in a single trip or if additional trips are needed.
- e. If return trips are needed, the destination of school buses should be No Refer to Section 2.4 provided.
- f. If used, reception centers should be identified. Discussion should be No provided on whether students are expected to pass through the reception center prior to being evacuated to their final destination.
- g. Supporting information should be provided to quantify the time elements No for the return trips.
4.2 ETE Modeling
- a. General information about the model should be provided and Yes Section 4.2 demonstrates its use in ETE studies.
- b. If a traffic simulation model is not used to conduct the ETE calculation, No Not Applicable sufficient detail should be provided to validate the analytical approach used. All criteria elements should have been met, as appropriate.
4.2.1 Traffic Simulation Model Input
- a. Traffic simulation model assumptions and a representative set of model Yes Section 4.2.1 inputs should be provided.
Appendix A
- b. A glossary of terms should be provided for the key performance measures Yes Section 6.0 and parameters used in the analysis.
4.2.2 Traffic Simulation Model Output
- a. A discussion regarding whether the traffic simulation model used must be Yes Section 4.3 in equilibration prior to calculating the ETE should be provided.
- b. The minimum following model outputs should be provided to support Yes Section 4.2.2 review:
- 1. Total volume and percent by hour at each EPZ exit node. Appendix C
- 2. Network-wide average travel time.
- 3. Longest queue length for the 10 intersections with the highest traffic volume.
- 4. Total vehicles exiting the network.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No)
- 5. A plot that provides both the mobilization curve and evacuation curve identifying the cumulative percentage of evacuees who have mobilized and exited the EPZ.
- 6. Average speed for each major evacuation route that exits the EPZ.
- c. Color coded roadway maps should be provided for various times (i.e., at 2, Yes Appendix A 4, 6 hrs., etc.) during a full EPZ evacuation scenario, identifying areas where long queues exist including level of service (LOS) E and LOS F conditions, if they occur.
4.3 Evacuation Time Estimates for the General Public
- a. The ETE should include the time to evacuate 90% and 100% of the total Yes Table 4.13 permanent resident and transient population.
Table 4.14
- b. The ETE for 100% of the general public should include all members of the Yes Statistical outliers related to trip generation time general public. Any reductions or truncated data should be explained. are addressed in Section 4.1
- c. Tables should be provided for the 90 and 100 percent ETEs similar to No Because this ETE analysis for the CRN Site Table 4-3, ETEs for Staged Evacuation Keyhole, of NUREG/CR-7002. considers an EPZ encompassing an approximate 2 mile radius around the proposed reactor center point location, staged and traditional keyhole evacuations are not appropriate for the CRN Site and have not been considered in this analysis.
Instead this analysis considers an evacuation of the entire EPZ for each evacuation scenario.
Refer to Section 1.3.1
- d. ETEs should be provided for the 100 percent evacuation of special Yes Table 4.11 facilities, transit dependent, and school populations.
Table 4.12 5.0 Other Considerations 5.1 Development of Traffic Control Plans
- a. Information that responsible authorities have approved the traffic control No Not Applicable plan used in the analysis should be provided.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No)
- b. A discussion of adjustments or additions to the traffic control plan that No Based on the low population of the EPZ, the affect the ETE should be provided. limited number of vehicles involved in the evacuation, the relative simplicity of the roadway network within the EPZ, and the absence of congestion observed during the traffic simulation modeling, the need to develop more detailed traffic control plans to support an evacuation is not considered necessary at this time.
5.2 Enhancements in Evacuation Time
- a. The results of assessments for improvement of evacuation time should be No Based on the absence of congestion observed provided. during the traffic simulation modeling, the need to
- b. A statement or discussion regarding presentation of enhancements to develop enhancements that may reduce local authorities should be provided. evacuation times would have little, if any, benefit.
5.3 State and Local Review
- a. A list of agencies contacted and the extent of interaction with these Yes Section 5.3 agencies should be discussed.
- b. Information should be provided on any unresolved issues that may affect No Not Applicable the ETE.
5.4 Reviews and Updates
- a. A discussion of when an updated ETE analysis is required to be performed Yes Section 5.6 and submitted to the NRC. Section 5.7 5.5 Reception Centers and Congregate Care Centers
- a. A map of congregate care centers and reception centers should be No The specific locations of reception centers have provided. not yet been identified.
- b. If return trips are required, assumptions used to estimate return times for No Because of the absence of a school population buses should be provided. and the limited number of transit-dependent permanent residents, it is not anticipated that multiple trips will be necessary to evacuate the transit dependent population.
- c. It should be clearly stated if it is assumed that passengers are left at the No It is not anticipated that multiple trips will be reception center and are taken by separate buses to the congregate care necessary to evacuate the transit dependent 105 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Criterion Addressed Comments in ETE Analysis (Yes/No) center. population. Therefore, the logistics of offloading passengers will not impact return trips to the EPZ or the evacuation time.
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Appendix C - Traffic Simulation Model Inputs and Outputs 107 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table C.1 Loading Curves Duration Scenario Time Period (Min) 1 2 3 4 5 6 7 8 9 10 1 15 10 9 5 0 7 7 2 0 10 167 2 15 66 64 89 79 56 53 79 72 66 275 3 15 111 109 210 209 96 95 195 192 111 245 4 15 106 108 158 172 98 97 151 158 106 244 5 15 137 139 131 144 131 132 124 134 137 303 6 15 142 142 77 77 138 138 71 72 142 316 7 15 117 116 41 40 112 112 39 36 117 291 8 15 76 75 19 17 74 73 15 16 76 252 9 15 39 38 18 20 29 29 20 17 39 214 10 15 33 33 16 12 41 41 12 12 33 214 11 15 11 11 5 7 9 9 7 4 11 193 12 15 11 11 10 8 13 13 8 9 11 187 13 15 3 3 1 0 5 5 1 0 3 182 14 15 5 5 2 1 2 2 0 0 5 186 15 15 3 3 0 1 4 3 0 0 3 182 16 15 4 4 0 0 4 4 2 1 4 141 17 15 0 0 0 0 0 0 0 0 0 0 18 15 0 0 0 0 0 0 0 0 0 0 19 15 0 0 0 0 0 0 0 0 0 0 20 15 0 0 0 0 1 1 0 0 0 0 108 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table C.2 Data Input by Zone Scenario Zones 1 2 3 4 5 6 7 8 9 10 226 308 300 275 250 293 288 263 250 308 312 51 341 334 279 251 330 325 267 251 341 349 59 203 213 205 262 175 179 174 203 203 208 186 10 11 12 10 11 11 10 9 10 12 188 10 10 9 12 11 11 10 10 10 2709 111 10 11 11 11 11 11 10 10 10 12 Table C.3 Destination Nodes and Capacities Destination Capacities Destination Capacities Destination Capacities 180 3800 201 1900 219 1900 134 1900 27 1900 98 1900 216 1900 227 7600 25 1900 139 3800 209 3800 174 1900 223 1900 147 1900 129 1900 23 3800 125 1900 119 1900 167 1900 22 4000 197 1900 33 1900 132 4000 221 1900 166 1900 215 1900 225 8000 109 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table C.4 Exiting Number of Vehicles by Hour by Exiting Node Time (Hour) Exiting Exiting Scenario From To Link Node 1 2 3 4 5 6 7 8 9 10 0 1 2495 913 135 128 179 152 120 115 162 153 135 636 0 1 504 892 43 52 104 141 34 37 88 111 43 45 0 1 1811 1801 94 86 159 131 82 74 144 134 94 97 1 2 2495 913 183 184 102 102 186 184 104 100 183 868 1 2 504 892 128 128 83 105 110 111 72 79 126 129 1 2 1811 1801 171 170 97 103 165 166 100 99 171 170 2 3 2495 913 39 38 20 20 38 39 22 17 39 752 2 3 504 892 28 29 17 16 26 27 13 13 30 30 2 3 1811 1801 37 38 16 14 40 42 18 16 37 39 3 4 2495 913 6 7 1 1 7 8 1 0 6 726 3 4 504 892 4 4 1 0 5 4 1 0 4 4 3 4 1811 1801 6 6 3 2 6 6 1 1 6 6 4 5 2495 913 0 0 0 0 1 1 0 0 0 90 4 5 504 892 0 0 0 0 0 0 0 0 0 0 4 5 1811 1801 0 0 0 0 0 0 0 0 0 0 110 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table C.5 Exiting Percentage of Vehicles by Hour by Exiting Node Time (Hour) Exiting Exiting Scenario From To Link Node 1 2 3 4 5 6 7 8 9 10 0 1 2495 913 15.4% 14.7% 22.9% 19.3% 14.6% 14.1% 22.3% 21.2% 15.4% 17.7%
0 1 504 892 4.9% 6.0% 13.3% 17.9% 4.1% 4.5% 12.1% 15.4% 4.9% 1.3%
0 1 1811 1801 10.8% 9.9% 20.3% 16.6% 10.0% 9.1% 19.8% 18.5% 10.8% 2.7%
1 2 2495 913 20.9% 21.1% 13.0% 13.0% 22.7% 22.6% 14.3% 13.8% 20.9% 24.2%
1 2 504 892 14.6% 14.7% 10.6% 13.3% 13.4% 13.6% 9.9% 10.9% 14.4% 3.6%
1 2 1811 1801 19.6% 19.5% 12.4% 13.1% 20.1% 20.4% 13.8% 13.7% 19.6% 4.7%
2 3 2495 913 4.5% 4.4% 2.6% 2.5% 4.6% 4.8% 3.0% 2.4% 4.5% 20.9%
2 3 504 892 3.2% 3.3% 2.2% 2.0% 3.2% 3.3% 1.8% 1.8% 3.4% 0.8%
2 3 1811 1801 4.2% 4.4% 2.0% 1.8% 4.9% 5.2% 2.5% 2.2% 4.2% 1.1%
3 4 2495 913 0.7% 0.8% 0.1% 0.1% 0.9% 1.0% 0.1% 0.0% 0.7% 20.2%
3 4 504 892 0.5% 0.5% 0.1% 0.0% 0.6% 0.5% 0.1% 0.0% 0.5% 0.1%
3 4 1811 1801 0.7% 0.7% 0.4% 0.3% 0.7% 0.7% 0.1% 0.1% 0.7% 0.2%
4 5 2495 913 0.0% 0.0% 0.0% 0.0% 0.1% 0.1% 0.0% 0.0% 0.0% 2.5%
4 5 504 892 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%
4 5 1811 1801 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0%
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Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table C.6 Network-Wide Travel Time (Minutes)
Scenario 1 2 3 4 5 6 7 8 9 10 2.57 2.99 2.59 2.57 2.57 3.90 2.59 2.59 2.84 9.22 112 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table C.7 Total Vehicles Exiting the Network Scenario Time Period Duration (Min) 1 2 3 4 5 6 7 8 9 10 1 15 9 8 5 0 6 6 2 0 9 167 2 15 51 53 72 66 46 39 66 56 51 275 3 15 109 105 186 187 94 92 171 164 110 245 4 15 103 100 179 171 90 89 155 178 102 244 5 15 134 132 132 154 133 129 136 132 134 303 6 15 141 146 78 85 137 138 82 82 141 316 7 15 119 119 47 51 112 112 42 44 119 291 8 15 88 85 25 20 79 82 16 20 88 252 9 15 44 45 19 22 35 38 25 18 44 214 10 15 33 31 17 11 44 39 11 12 33 214 11 15 15 18 8 9 14 20 8 7 15 193 12 15 12 11 9 8 11 11 9 9 12 187 13 15 4 5 3 1 8 9 1 0 4 182 14 15 4 4 2 1 1 1 0 0 4 186 15 15 4 3 0 1 5 4 0 0 4 182 16 15 4 5 0 0 4 4 2 1 4 141 17 15 0 0 0 0 0 0 0 0 0 0 18 15 0 0 0 0 0 0 0 0 0 0 19 15 0 0 0 0 0 0 0 0 0 0 20 15 0 0 0 0 1 1 0 0 0 0 Total 874 870 782 787 820 814 726 723 874 3592 113 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure C.1 Mobilization and Evacuation Curves 114 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Table C.8 Average Speeds for Major Evacuation Routes (mph)
Scenario Route 1 2 3 4 5 6 7 8 9 10 Route 58 49 42 50 50 49 32 50 50 49 48 I-40 63 54 63 63 63 41 63 63 63 63 115 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Figure C.2 Time Lapse Simulation Graphics Simulation Screenshot 1 - Background Traffic 116 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Simulation Screenshot 2 - ~ 30 minutes after Order to Evacuate 117 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Simulation Screenshot 3 - ~ 90 minutes after Order to Evacuate 118 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Simulation Screenshot 4 - ~ 115 minutes after Order to Evacuate 119 Revision 0
Clinch River Nuclear Site Early Site Permit Application Part 5B, Emergency Plan Evacuation Time Estimate Simulation Screenshot - ~ 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after Order to Evacuate 120 Revision 0